Accreditation proposal for control systems in electrical engineering for 6th level in European Qualification Framework (EQF)

DEFF Research Database (Denmark)

Tsirigotis, Georgios; Friesel, Anna

2013-01-01

The progress of science and technology emphasizes the connection between different domains and disciplines. The technology development and changing demands of the labour market require upgrading and renewing of learning outcomes in higher education, especially in engineering fields. The Life Long...... Learning (LLL) procedure must be the platform offering the required qualifications for the demands of companies and engineering professionals all over the world in order to support their competitiveness. In this paper we describe an improved proposal for accreditation of one important subject...... in engineering, namely Control Systems. The described procedure could be applied in the frame of LLL and also in classical engineering education systems, such as university and college education, in order to harmonize the recognition of engineering degrees in Europe and outside the Europe. Furthermore we state...

The use of case tools in OPG safety analysis code qualification

International Nuclear Information System (INIS)

Pascoe, J.; Cheung, A.; Westbye, C.

2001-01-01

Ontario Power Generation (OPG) is currently qualifying its critical safety analysis software. The software quality assurance (SQA) framework is described. Given the legacy nature of much of the safety analysis software the reverse engineering methodology has been adopted. The safety analysis suite of codes was developed over a period of many years to differing standards of quality and had sparse or incomplete documentation. Key elements of the reverse engineering process require recovery of design information from existing coding. This recovery, if performed manually, could represent an enormous effort. Driven by a need to maximize productivity and enhance the repeatability and objectivity of software qualification activities the decision was made to acquire or develop and implement Computer Aided Software Engineering (CASE) tools. This paper presents relevant background information on CASE tools and discusses how the OPG SQA requirements were used to assess the suitability of available CASE tools. Key findings from the application of CASE tools to the qualification of the OPG safety analysis software are discussed. (author)

Qualifications of Food Science and Technology/Engineering professionals at the entrance in the job market

Directory of Open Access Journals (Sweden)

Virginia Giannou

2015-10-01

Full Text Available The qualifications of Food Science and Technology/Engineering (FST/E professionals were examined by a web-based survey conducted in 15 countries (14 EU and Turkey. The analysis of the responses showed that 65% of the respondents had a higher education (HE degree (BSc 29%, MSc 28%, and PhD 8%, and 20% carried out extracurricular training before entering in the job market. The main fields of study were Food Science and Technology/Engineering, followed by Agriculture, Nutrition and Health, Safety/Hygiene, and Chemical Engineering in all three levels of HE degrees. Differences in the level of degree between genders were not observed, although a higher percentage of female respondents (36% of all female respondents reported no higher qualification degree, compared to male respondents (33% of all male respondents. On the contrary, female respondents prevailed in extracurricular studies, compared to male ones. Gender, however, was a differentiating factor as far as the field of studies was concerned with female respondents prevailing in Nutrition and Health and male in Agriculture.A considerable percentage of the respondents acquired either a ΗΕ degree or had extracurricular training while working in the 1st job. Extracurricular training both before entering the job market and during work at the 1st workplace comprised mainly the topics Safety and Hygiene, Management, followed by Sensory Science, FST/E and Nutrition and Health. In addition, Marketing Science/Consumer Behaviour was also one of the main topics of company or other training during work at the 1st workplace.   

Recent developments in methodology for dynamic qualification of nuclear plant equipment

International Nuclear Information System (INIS)

Kana, D.D.; Pomerening, D.J.

1984-01-01

Dynamic qualification of nuclear plant electrical and mechanical equipment is performed basically under guidelines given in IEEE Standards 323 and 344, and a variety of NRC regulatory guides. Over the last fifteen years qualification methodology prescribed by these documents has changed significantly as interpretations, equipment capability, and imagination of the qualification engineers have progressed. This progress has been sparked by concurrent NRC and industry sponsored research programs that have identified anomalies and developed new methodologies for resolving them. Revisions of the standards have only resulted after a lengthy debate of all such new information and subsequent judgment of its validity. The purpose of this paper is to review a variety of procedural improvements and developments in qualification methodology that are under current consideration as revisions to the standards. Many of the improvements and developments have resulted from recent research programs. All are very likely to appear in one type of standard or another in the near future

Seismic qualification of equipment for the TA-55 Plutonium Processing Facility

International Nuclear Information System (INIS)

Pellette, P.R.; Endebrock, E.G.; Giles, P.M.; Shaw, R.H.

1977-04-01

The techniques employed by the Los Alamos Scientific Laboratory (LASL) for the seismic qualification of internal equipment for the TA-55 Plutonium Facility are discussed. The structural analysis of the plutonium building and critical associated structures was performed by the Architect-Engineer (A-E), and the calculations were checked by LASL. The specifications and procedures used by LASL produced dramatic improvement in the responses by qualified vendors to the seismic requirements. There was an increase from about a 20% bid ratio to greater than 90% because prospective vendors could be competitive without having had previous seismic experience with their equipment. The equipment seismic qualification for TA-55 is in compliance with the Code of Federal Regulations, Nuclear Regulatory Commission (NRC) Guides, Energy Research and Development Administration (ERDA) Manual Chapters and Appendices, and Institute of Electrical and Electronic Engineers (IEEE) Standard 344

Overview of the IAEA's activity on ISI qualification

International Nuclear Information System (INIS)

Trampus, P.

2000-01-01

The IAEA Subprogram on Nuclear Power Planning, Implementation and Performance is presented. It's objective is to assist Member States in: planning nuclear power programmes in an integrated manner considering all necessary factors; systematically improving overall performance and competitiveness of NPPs trough entire service life with due regard to safety; applying technological/engineering best practices including QA/QM in all areas of nuclear power utilisation. International working group on life management of NPPs (IWG-LMNPP) has been established in 1975 with 26 Member States and 2 international organizations in order to provide the Director General with advice and opinions and the Member States with information, recommendations and support in life management issues.The technical co-operation program RER/4/020 'Advanced NDT of Primary Circuit Components' is presented.The pilot study is aimed to provide the participating Member States with practical advice how to apply the IAEA's qualification methodology. The target application is Technical Justification for UT of WWER-1000 RPV shell weld (unit 5 of 'Kozloduy NPP). The concept is to simulate the qualification process through assistance to establish qualification for a real NPP component, using real ISI, in a real regulatory environment. Interim results for Bulgaria are reported and further tasks are outlined

Seismic qualification testing at the National Engineering Laboratory

International Nuclear Information System (INIS)

Fairbairn, J.

1984-01-01

Servohydraulic shaker tables have been developed for the simulation of vibration environments including earthquakes. The use of these facilities for seismic qualification of nuclear equipment is described. (author)

Unintended Consequences: How Qualification Constrains Innovation

Science.gov (United States)

Brice, Craig A.

2011-01-01

The development and implementation of new materials and manufacturing processes for aerospace application is often hindered by the high cost and long time span associated with current qualification procedures. The data requirements necessary for material and process qualification are extensive and often require millions of dollars and multiple years to complete. Furthermore, these qualification data can become obsolete for even minor changes to the processing route. This burden is a serious impediment to the pursuit of revolutionary new materials and more affordable processing methods for air vehicle structures. The application of integrated computational materials engineering methods to this problem can help to reduce the barriers to rapid insertion of new materials and processes. By establishing predictive capability for the development of microstructural features in relation to processing and relating this to critical property characteristics, a streamlined approach to qualification is possible. This paper critically examines the advantages and challenges to a modeling-assisted qualification approach for aerospace structural materials. An example of how this approach might apply towards the emerging field of additive manufacturing is discussed in detail.

Engineering qualifications for competence

International Nuclear Information System (INIS)

Levy, J.C.

1990-01-01

The Engineering Council has a responsibility across all fields of engineering to set standards for those who are registered as Chartered Engineers, Incorporated Engineers or Engineering Technicians. These standards amount to a basic specification of professional competence to which must be added the features needed in each different branch of engineering, such as nuclear, and each particular occupation, such as quality assurance. This article describes The Engineering Council's general standards and includes a guide to the roles and responsibilities which should lie within the domain of those who are registered with the Council. The concluding section describes the title of European Engineer and its relationship to the European Community directive governing the movement of professionals across community frontiers. (author)

Test-qualification experience with non-destructive material analysis system performed at Paks Nuclear Power Plant and its usage in non-nuclear fields

International Nuclear Information System (INIS)

Somogyi, Gy.; Szabo, D.

2003-01-01

The need for qualification of non-destructive material analysis has been recognised in controlling nuclear energy production process. This test-qualification has been performed as first of its kind after the task has been assigned by the National Nuclear Energy Agency. The input documents for the test were. Technical Specification, Analysis Technology, Technical Justification. Test-qualification has been performed with real form control bodies developed by the Rez Nuclear Research Institute, in which the planned defects has been produced by spark-chipping. The qualification procedure has been summarized in a Qualification Folder and given to the national agency to issue a qualification certificate. The procedure might be interesting mostly for companies delivering nuclear power plant assemblies. Similar needs are formulated in standards relative to the qualification of non-nuclear material testing methods (MSZ EN 17025 and EU). (Gy.M.)

LTP fibre injector qualification and status

International Nuclear Information System (INIS)

Bogenstahl, J; Cunningham, L; Fitzsimons, E D; Hough, J; Killow, C J; Perreur-Lloyd, M; Robertson, D; Rowan, S; Ward, H

2009-01-01

This paper presents the current state of the LISA Technology Package (LTP) fibre injector qualification project in terms of vibration and shock tests. The fibre injector is a custom built part and therefore must undergo a full space qualification process. The mounting structure and method for sinusoidal vibration and random vibration tests as well as shock tests will be presented. Furthermore a proposal will be presented to use the fibre injector pair qualification model to build an optical prototype bench. The optical prototype bench is a full-scale model of the flight model. It will be used for development and rehearsal of all the assembly stages of the flight model and will provide an on-ground simulator for investigation as an updated engineering model.

Development, structure and qualification of a new digital instrumentation and control system

International Nuclear Information System (INIS)

Hofmann, H.; Sauer, H.J.

1991-01-01

Introduction of digital instrumentation and control in nuclear power plants is characterized by the need to meet numerous requirements concerning reliability, ergonomic design of the main control room and comprehensive qualification. The system described here is distinguished by a hierarchical and modular structure, being redundant throughout. Ergonomic considerations dominate the layout of the screen-based main control room. Powerful computer-aided engineering tools are employed for planning of the entire system and for generation of the user software. Qualification is performed in step with the development of the system, based on the applicable national and international rules and regulations and in close cooperation with an independent expert. (orig.) [de

Development of Simulator Maintenance Engineer Qualification Program Draft

International Nuclear Information System (INIS)

Chung, Kyung Hun

2010-01-01

As of 2009, KHNP has currently seven full scope simulators that are used for training of Nuclear Power Plant (NPP) Operators. Well-trained Simulator Maintenance Engineers (SME) are required to support these simulators. These SMEs will maintain and address any issues identified or any changes required for keep up the simulator with their respective plant sites. These issues will be identified as Simulator Discrepancy Reports (DR) or Work Order (WO) by the simulator operation personnel in KHNP. The simulator maintenance is a very complex. The simulator consists of many areas of process and requires experts in software modeling for different processes such as Neutronics, thermohydraulics, Logics, control, Electrical systems and computer systems as well as hardware subjects such as I and C, I/O, computers, etc. All these areas need experts the subject expertise need to be divided among SME's. In other word the SME's need to be trained for different expertise as well as having different level of SME's. KHNP has seen the need to outsource the maintenance work for these complex simulators. To have one company concentrating on this work will have many benefits such as: · Provides proper and well trained experts · Maintains consistent support personnel · Maintains the maintenance history for the simulator · Coordinates and Maintains the knowledge in house · The simulator maintenance will be consistent In order to accomplish the goals, KEPCO RI has recognized that there is a need for a program to adequately train and qualify the SME's. KEPCO RI and GSE, which has provided 6 simulators among 7 NPP simulators in Korea, have jointly developed this Simulator Maintenance Engineer Qualification Program (SMEQP). After issue of this plan, KEPCO RI will maintain and modify as needed periodically to meet the goals and purpose of the plan

Qualification test and analysis report: solar collectors

Energy Technology Data Exchange (ETDEWEB)

1978-12-01

Test results show that the Owens-Illinois Sunpak/sup TM/ Model SEC 601 air-cooled collector meets the national standards and codes as defined in the Subsystem Performance Specification and Verification Plan of NASA/MSFC Contract NAS8-32259, dated October 28, 1976. The architectural and engineering firm of Smith, Hinchman and Grylls, Detroit, Michigan, acted in the capacity of the independent certification agency. The program calls for the development, fabrication, qualification and delivery of an air-liquid solar collector for solar heating, combined heating and cooling, and/or hot water systems.

Equipment qualification testing - a practical approach

International Nuclear Information System (INIS)

Davies, G.A.; McDougall, R.I.; Poirier, M.P.

1996-01-01

When nuclear safety equipment is credited with a Required Safety Function it must properly perform that function to facilitate safe control and/or shutdown of the plant during a design basis accident. When such equipment is required to be environmentally (EQ) and/or seismically qualified (SQ) for safety related use in CANDU nuclear power plants, the preferred method of qualification is by type testing. The qualification testing process requires that the test specimen equipment be subjected to the aging stressors associated with the normal service conditions that it would experience during it's required qualified (or service) life. Following the aging process, the test specimen is in a condition representative of that in which it would be at the end of its service life in the plant. The test specimen is then subjected to a simulated accident during which it must satisfy performance requirements thereby demonstrating that it can perform its required safety function. The performance requirements specified for the qualification testing must be designed to ensure that satisfactory performance of the safety function is demonstrated during the qualification program. This paper provides descriptions of practical methods used in the deriving and satisfying of relevant performance requirements during the qualification testing of safety related equipment. (author)

Process qualification and testing of LENS deposited AY1E0125 D-bottle brackets

International Nuclear Information System (INIS)

Atwood, Clinton J.; Smugeresky, John E.; Jew, Michael; Gill, David Dennis; Scheffel, Simon

2006-01-01

The LENS Qualification team had the goal of performing a process qualification for the Laser Engineered Net Shaping(trademark)(LENS(reg s ign)) process. Process Qualification requires that a part be selected for process demonstration. The AY1E0125 D-Bottle Bracket from the W80-3 was selected for this work. The repeatability of the LENS process was baselined to determine process parameters. Six D-Bottle brackets were deposited using LENS, machined to final dimensions, and tested in comparison to conventionally processed brackets. The tests, taken from ES1E0003, included a mass analysis and structural dynamic testing including free-free and assembly-level modal tests, and Haversine shock tests. The LENS brackets performed with very similar characteristics to the conventionally processed brackets. Based on the results of the testing, it was concluded that the performance of the brackets made them eligible for parallel path testing in subsystem level tests. The testing results and process rigor qualified the LENS process as detailed in EER200638525A

Discrete Data Qualification System and Method Comprising Noise Series Fault Detection

Science.gov (United States)

Fulton, Christopher; Wong, Edmond; Melcher, Kevin; Bickford, Randall

2013-01-01

A Sensor Data Qualification (SDQ) function has been developed that allows the onboard flight computers on NASA s launch vehicles to determine the validity of sensor data to ensure that critical safety and operational decisions are not based on faulty sensor data. This SDQ function includes a novel noise series fault detection algorithm for qualification of the output data from LO2 and LH2 low-level liquid sensors. These sensors are positioned in a launch vehicle s propellant tanks in order to detect propellant depletion during a rocket engine s boost operating phase. This detection capability can prevent the catastrophic situation where the engine operates without propellant. The output from each LO2 and LH2 low-level liquid sensor is a discrete valued signal that is expected to be in either of two states, depending on whether the sensor is immersed (wet) or exposed (dry). Conventional methods for sensor data qualification, such as threshold limit checking, are not effective for this type of signal due to its discrete binary-state nature. To address this data qualification challenge, a noise computation and evaluation method, also known as a noise fault detector, was developed to detect unreasonable statistical characteristics in the discrete data stream. The method operates on a time series of discrete data observations over a moving window of data points and performs a continuous examination of the resulting observation stream to identify the presence of anomalous characteristics. If the method determines the existence of anomalous results, the data from the sensor is disqualified for use by other monitoring or control functions.

Radiated EMC& EMI Management During Design Qualification and Test Phases on LEO Satellites Constellation

Science.gov (United States)

Blondeaux, H.; Terral, M.; Gutierrez-Galvan, R.; Baud, C.

2016-05-01

The aim of the proposed paper is to present the global radiated EMC/EMI approach applied by Thales Alenia Space in the frame of a telecommunication Low Earth Orbit (LEO) satellites constellation program. The paper will present this approach in term of analyses, of specific characterisation and of sub-system and satellite tests since first design reviews up-to satellite qualification tests on Prototype Flight Model (PFM) and to production tests on reduced FMs. The global aim is : 1 - to reduce risk and cost (units EMC delta qualification, EMC tests at satellite level for the 81 Space Vehicles (SV) through appropriated EMC analyses (in term of methodologies and contours) provided in the frame of design reviews.2 - to early anticipate potential critical case to reduce the impact in term of engineering/qualification/test extra cost and of schedule.3 - to secure/assure the payload and SV design/layout.4 - to define and optimize the EMC/EMI test campaigns to be performed on Prototype Flight Model (PFM) for complete qualification and on some FMs for industrial qualification/validation.The last part of the paper is dedicated to system Bite Error Rate (BER) functional test performed on PFM SV to demonstrate the final compatibility between the three on-board payloads and to the Internal EMC tests performed on PFM and some FMs to demonstrate the SV panel RF shielding efficiency before and after environmental tests and the Thales Alenia Space (TAS) and Orbital AKT (OATK) workmanships reproducibility.

The french safety approach regarding equipment qualification

International Nuclear Information System (INIS)

Jalouneix, J.; Deletre, G.; Henry, J.Y.; Rousseau, L.

1989-10-01

The qualification of the equipment, used in France on nuclear reactors and reactor components, is discussed. The approach on safety involves the qualification of mechanical and electrical components, under operating and under seismic conditions. The principles of the qualification program and the list of the equipment concerned, are given. The conditions in which qualification tests are performed and the methods applied, are summarized. The actions for preserving the qualification procedures, are considered

Qualification of ISI for Bulgarian NPP: UK support

International Nuclear Information System (INIS)

Booler, R.

2000-01-01

UK Regulator (NII) Phare project provides an assistance to the Bulgarian Regulator in setting up the technical infrastructure for inspection qualification consistent with IAEA Guidelines and western European practice. The Strategy Document defines the methodology for inspection qualification and general roles and responsibilities of the involved organizations. The Qualification Inputs Document describes the information required for the Technical Specifications (component details, inspection aims and limitations). It applies the idea of qualification level - level 1(lowest) to level 3 (highest). The Qualification Procedure Document provides a guidance to the utility ('Kozloduy' NPP) on the preparation of Qualification Procedures (QP). The appendix provides a specific guidance on the performance of the all aspects of qualification at different levels and recommendations for technical justification. QB Method Working Document provides guidance for the Qualification Body. Facilities and Resources Document defines the facilities and resources required for the Qualification Body to perform the tasks described in the Method Working Document. High level QA Document defines the principles of quality control. Other issues and progress report are also presented

Prevalence of GMC performance assessments in the United Kingdom: a retrospective cohort analysis by country of medical qualification.

Science.gov (United States)

Mehdizadeh, L; Potts, H W W; Sturrock, A; Dacre, J

2017-04-04

The demographics of doctors working in the UK are changing. The United Kingdom (UK) has voted to leave the European Union (EU) and there is heightened political discourse around the world about the impact of migration on healthcare services. Previous work suggests that foreign trained doctors perform worse than UK graduates in postgraduate medical examinations. We analysed the prevalence by country of primary medical qualification of doctors who were required to take an assessment by the General Medical Council (GMC) because of performance concerns. This was a retrospective cohort analysis of data routinely collected by the GMC. We compared doctors who had a GMC performance assessment between 1996 and 2013 with the medical register in the same period. The outcome measures were numbers experiencing performance assessments by country or region of medical qualification. The rate of performance assessment varied significantly by place of medical qualification and by year; χ 2 (17) = 188, p Economic Area (EEA), were more likely to have a performance assessment than UK trained doctors, with the exception of South African trained doctors. The rate of performance assessment varies significantly by place of medical qualification. This is the first study to explore the risk of performance assessment by individual places of medical qualification. While concern has largely focused on the competence of non-EEA, International Medical Graduates, we discuss implications for how to ensure European trained doctors are fit to practise before their medical licence in the UK is granted. Further research is needed to investigate whether these country effects hold true when controlling for factors like doctors' sex, age, length of time working in the UK, and English language skills. This will allow evidence-based decisions to be made around the regulatory environment the UK should adopt once it leaves the EU. Patients should be reassured that the vast majority of all doctors

Nuclear EQ sourcebook: A compilation of documents for nuclear equipment qualification

International Nuclear Information System (INIS)

Anon.

1992-01-01

In the nuclear power industry, environmental and seismic qualification of safety-related electrical and instrumentation equipment is collectively known as Equipment Qualification (EQ). Related technology, as well as regulatory requirements, have evolved rapidly during the last 15 years. For environmental qualification, what began in 1971 with one trial-use guide (IEEE Std 323-1971), now stands as a full complement of Nuclear Regulatory Commission (NRC) rules, guides and industry standards. In addition to the Institute of Electrical and Electronics Engineers (IEEE), the American Society of Mechanical Engineers (ASME) has also undertaken development of its own set of standards for use in qualifying safety-related mechanical equipment. To ensure that the original design and qualification is preserved, engineers need to select and use the correct set of NRC regulations, regulatory guides, industry standards, and generic correspondence. Given that the total number of these documents exceed 200, this task becomes resource intensive. This compilation is the first known publication available to serve the user-community need for a complete and exhaustive single source. Approximately 180 items (Bulletins, Federal Rules, Generic Letters, Notices, Regulatory Guides, IEEE Standards, IEEE Recommended Practices, and IEEE Guides) have been processed separately for inclusion on the data base

AGR-1 Data Qualification Report

International Nuclear Information System (INIS)

Abbott, Michael

2010-01-01

Projects for the very high temperature reactor (VHTR) Technology Development Office (TDO) program provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR program has established the NGNP Data Management and Analysis System (NDMAS) to ensure that VHTR data are (1) qualified for use, (2) stored in a readily accessible electronic form, and (3) analyzed to extract useful results. This document focuses on the first NDMAS objective. It describes the data streams associated with the first Advanced Gas Reactor experiment (AGR-1), the processing of these data within NDMAS, and reports the qualification status of the data. Data qualification activities within NDMAS for specific types of data are determined by the data qualification category assigned by the data generator. They include: (1) capture testing, to confirm that the data stored within NDMAS are identical to the raw data supplied, (2) accuracy testing, to confirm that the data are an accurate representation of the system or object being measured, and (3) documentation that the data were collected under an NQA-1 or equivalent quality assurance program. The NDMAS database processing and qualification status of the following five data streams is reported in this document: (1) Fuel fabrication data. All data have been processed into the NDMAS database and qualified (1,819 records). (2) Fuel irradiation data. Data from all 13 AGR-1 reactor cycles have been processed into the NDMAS database and tested. Of these, 85% have been qualified and 15% have failed NDMAS accuracy testing. (3) FPMS data. Reprocessed (January 2010) data from all 13 AGR-1 reactor cycles have been processed into the database and capture tested. Final qualification of these data will be recorded after QA approval of an Engineering Calculations and Analysis Report currently

Advanced qualification methodology for actively cooled plasma facing components

Science.gov (United States)

Durocher, A.; Escourbiac, F.; Grosman, A.; Boscary, J.; Merola, M.; Cismondi, F.; Courtois, X.; Farjon, J. L.; Missirlian, M.; Schlosser, J.; Tivey, R.

2007-12-01

The use of high heat flux plasma facing components (PFCs) in steady state fusion devices requires high reliability. These components have to withstand heat fluxes in the range 10-20 MW m-2 involving a number of severe engineering constraints. Feedback from the experience of various industrial manufacturings showed that the bonding of the refractory armour material onto the metallic heat sink causes generic difficulties strongly depending on material qualities and specific design. As the heat exhaust capability and lifetime of PFCs during plasma operation are directly linked to the manufacturing quality, a set of qualification activities such as active infrared thermography, lock-in and acoustic measurements were performed during the component development phases following a qualification route. This paper describes the major improvements stemming from better measurement accuracy and refined data processing and analyses recent developments aimed at investigating the capability to qualify the component in situ during its lifetime.

Advanced qualification methodology for actively cooled plasma facing components

International Nuclear Information System (INIS)

Durocher, A.; Escourbiac, F.; Grosman, A.; Boscary, J.; Merola, M.; Cismondi, F.; Courtois, X.; Farjon, J.L.; Missirlian, M.; Schlosser, J.; Tivey, R.

2007-01-01

The use of high heat flux plasma facing components (PFCs) in steady state fusion devices requires high reliability. These components have to withstand heat fluxes in the range 10-20 MW m -2 involving a number of severe engineering constraints. Feedback from the experience of various industrial manufacturings showed that the bonding of the refractory armour material onto the metallic heat sink causes generic difficulties strongly depending on material qualities and specific design. As the heat exhaust capability and lifetime of PFCs during plasma operation are directly linked to the manufacturing quality, a set of qualification activities such as active infrared thermography, lock-in and acoustic measurements were performed during the component development phases following a qualification route. This paper describes the major improvements stemming from better measurement accuracy and refined data processing and analyses recent developments aimed at investigating the capability to qualify the component in situ during its lifetime

STEM Leadership Qualification: Tomorrow's Leaders Today

Science.gov (United States)

Williams, Chris

2009-01-01

This article features the Science, Technology, Engineering and Mathematics (STEM) Leadership Qualification programme, developed by the Centre for Science Education (CSE) at Sheffield Hallam University in collaboration with Edexcel, which sets out to develop leadership skills and capabilities through contexts in STEM. With six units to complete…

Qualification program of the ASTRID SFR project: definition, methodology and associated risk evaluation and management - 15093

International Nuclear Information System (INIS)

Rodriguez, G.; Dirat, J.F.; Traina, A.; Christofari, M.

2015-01-01

The Preconceptual Design phase of the ASTRID French Sodium Fast Reactor project had the objective to integrate innovative options to meet the requirements of the 4. generation reactors and to comply with the related specifications. It was followed by the conceptual phase studies (AVP2 phase 2013-2015) where some technical options are left opened with an advanced option and a backup alternative. In the same time of the AVP2 phase studies, the qualification program related to ASTRID project was initiated. It consists in collecting the exhaustive list of research/development (R/D) needs and technological demonstration tests to be fulfilled on representative mockup prior to component implementation in the prototype. The ASTRID Qualification Program (AQP) objectives are to collect needs expressed by all engineering companies involved in ASTRID, and then to organize the answer to this expression of needs. This significant work of needs compilation has been divided in several tasks, according to the ASTRID project decomposition in the Product Breakdown Structure (PBS). Compilation of needs was jointly performed by engineering company, R/D responsible and coordinated by the ASTRID Qualification project responsible. It was associated with an evaluation of the maturity level of the technical options thanks to a Technological Readiness Level grid (TRL ranking table), an identification of major risks, and an evaluation of the R/D potentiality and associated facility platform. The methodology applied for the ASTRID Qualification Program (AQP) is presented. It is explained what methodology was used associated to the TRL process, and how is managed the associated risk analysis evaluation: evaluation of major risks, definition of a risk portfolio and a corresponding Action Plan for risk reduction (synthesized under the REM acronym: Risk Evaluation and Management). This methodology is a mean used to facilitate ASTRID risk-informed decision making, technology qualification and

Equipment qualification testing methodology research at Sandia Laboratories

International Nuclear Information System (INIS)

Jeppesen, D.

1983-01-01

The Equipment Qualification Research Testing (EQRT) program is an evolutionary outgrowth of the Qualification Testing Evaluation (QTE) program at Sandia. The primary emphasis of the program has been qualification methodology research. The EQRT program offers to the industry a research-oriented perspective on qualification-related component performance, as well as refinements to component testing standards which are based upon actual component testing research

Qualification of box HEPA filters for nuclear applications

International Nuclear Information System (INIS)

Bergman, W.; Larsen, G.; Wilson, K.; Rainer, F.

1995-03-01

We have successfully completed qualification tests on high efficiency particulate air (HEPA) filters that are encapsulated within a box and manufactured by American Air Filters. The qualification tests are required by the American Society of Mechanical Engineers Standard ASME N509 and the U.S. Military Standard MIL-F-51068 for HEPA filters to be used in nuclear applications. The qualification tests specify minimum filter efficiencies following exposure to heated air, overpressure, and rough handling. Prior to this study, no box HEPA filters from any manufacturer had been qualified despite their wide-spread use in Department of Energy (DOE) facilities. Box HEPA filters are not addressed in any of the existing HEPA standards and only briefly discussed in the Nuclear Air Cleaning Handbook

Data Qualification guidelines

International Nuclear Information System (INIS)

Edwards, T.B.; Shine, E.P.

1992-01-01

Data Qualification (DQ) is a formal, technical process whose objective is to affirm that experimental data are suitable for their intended use. Although it is not possible to develop a fixed recipe for the DQ process to cover all test situations, these general guidelines have been developed for the Nuclear Engineering Section to establish a framework for qualifying data from steady-state processing. These guidelines outline the role of the DQ team providing insight into the planning and conducting of the DQ process

Qualification tests for PWR control element drive mechanism

Energy Technology Data Exchange (ETDEWEB)

Kim, In Yong; Jin, Choon Eon; Choi Suhn [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1996-01-01

It is necessary to perform the qualification test for the magnetic jack type CEDM to show the design compatibility because the CEDM is composed of many mechanical and electrical components complicatedly. ABB-CE performed various qualification tests during the development of the System80 CEDM to which Korea Standard Nuclear Plant (KSNP) CEDM referred. The qualification test for the CEDM is classified into the performance test and the dynamic test. The performance test is to verify operability of the CEDM, and the dynamic test is to find dynamic characteristics and to verify the structural integrity if the CEDM for the seismic accidents. Described in this report are the test requirements, the test facilities and the test methods for the performance and the dynamic qualification tests of the PWR magnetic jack type CEDM. The impacts of the design changes in the Korea Next Generation Reactor (KNGR) on the KSNP CEDM were analyzed to present the necessity for the tests. This report also proposes the facilities to perform the tests in KAERI including reasonable schedule for the tests. Attached to this report is the summary of qualification tests of System 80 CEDM performed by ABB-CE. 20 figs., 16 tabs., 21 refs. (Author) .new.

Qualification tests for PWR control element drive mechanism

International Nuclear Information System (INIS)

Kim, In Yong; Jin, Choon Eon; Choi Suhn

1996-01-01

It is necessary to perform the qualification test for the magnetic jack type CEDM to show the design compatibility because the CEDM is composed of many mechanical and electrical components complicatedly. ABB-CE performed various qualification tests during the development of the System80 CEDM to which Korea Standard Nuclear Plant (KSNP) CEDM referred. The qualification test for the CEDM is classified into the performance test and the dynamic test. The performance test is to verify operability of the CEDM, and the dynamic test is to find dynamic characteristics and to verify the structural integrity if the CEDM for the seismic accidents. Described in this report are the test requirements, the test facilities and the test methods for the performance and the dynamic qualification tests of the PWR magnetic jack type CEDM. The impacts of the design changes in the Korea Next Generation Reactor (KNGR) on the KSNP CEDM were analyzed to present the necessity for the tests. This report also proposes the facilities to perform the tests in KAERI including reasonable schedule for the tests. Attached to this report is the summary of qualification tests of System 80 CEDM performed by ABB-CE. 20 figs., 16 tabs., 21 refs. (Author) .new

Performance and Environmental Test Results of the High Voltage Hall Accelerator Engineering Development Unit

Science.gov (United States)

Kamhawi, Hani; Haag, Thomas; Huang, Wensheng; Shastry, Rohit; Pinero, Luis; Peterson, Todd; Mathers, Alex

2012-01-01

NASA Science Mission Directorate's In-Space Propulsion Technology Program is sponsoring the development of a 3.5 kW-class engineering development unit Hall thruster for implementation in NASA science and exploration missions. NASA Glenn and Aerojet are developing a high fidelity high voltage Hall accelerator that can achieve specific impulse magnitudes greater than 2,700 seconds and xenon throughput capability in excess of 300 kilograms. Performance, plume mappings, thermal characterization, and vibration tests of the high voltage Hall accelerator engineering development unit have been performed. Performance test results indicated that at 3.9 kW the thruster achieved a total thrust efficiency and specific impulse of 58%, and 2,700 sec, respectively. Thermal characterization tests indicated that the thruster component temperatures were within the prescribed material maximum operating temperature limits during full power thruster operation. Finally, thruster vibration tests indicated that the thruster survived the 3-axes qualification full-level random vibration test series. Pre and post-vibration test performance mappings indicated almost identical thruster performance. Finally, an update on the development progress of a power processing unit and a xenon feed system is provided.

Internal qualification and credentialing of radiation oncology physicists to perform patient special procedures

Directory of Open Access Journals (Sweden)

Michael D Mills

2014-01-01

Full Text Available In the arena of radiation oncology special procedures, medical physicists are often the focus professionals for implementation and administration of advanced and complex technologies. One of the most vexing and challenging aspects of managing complexity concerns the ongoing internal qualification and credentialing of radiation oncology physicists to perform patient special procedures. To demonstrate ongoing qualification, a physicist must a document initial training and successful completion of competencies to implement and perform this procedure, b demonstrate familiarity with all aspects of the commissioning and quality assurance process, c demonstrate continuing education respecting this procedure, d demonstrate the peer-reviewed completion of a minimum number of patient special procedures during a specified time span, and e demonstrate satisfactory overall progress toward maintenance of specialty board certification. In many respects, this information complement is similar to that required by an accredited residency program in therapy physics. In this investigation, we report on the design of a management tool to qualify staff radiation oncology physicists to deliver patient procedures.

Data Qualification Report For: Thermodynamic Data File, DATA0.YMP.R0 For Geochemical Code, EQ3/6?

International Nuclear Information System (INIS)

P.L. Cloke

2000-09-01

The objective of this work is to evaluate the adequacy of chemical thermodynamic data provided by Lawrence Livermore National Laboratory (LLNL) as DataO.ymp.ROA in response to an input request submitted under AP-3.14Q. This request specified that chemical thermodynamic data available in the file, Data0.com.R2, be updated, improved, and augmented for use in geochemical modeling used in Process Model Reports (PMRs) for Engineered Barrier Systems, Waste Form, Waste Package, Unsaturated Zone, and Near Field Environment, as well as for Performance Assessment. The data are qualified in the temperature range 0 to 100 C. Several Data Tracking Numbers (DTNs) associated with Analysis/Model Reports (AMR) addressing various aspects of the post-closure chemical behavior of the waste package and the Engineered Barrier System that rely on EQ316 outputs to which these data are used as input, are Principal Factor affecting. This qualification activity was accomplished in accordance with the AP-SIII.2Q using the Technical Assessment method. A development plan, TDP-EBS-MD-000044, was prepared in accordance with AP-2.13Q and approved by the Responsible Manager. In addition, a Process Control Evaluation was performed in accordance with AP-SV.1Q. The qualification method, selected in accordance with AP-SIII.2Q, was Technical Assessment. The rationale for this approach is that the data in File Data0.com.R2 are considered Handbook data and therefore do not themselves require qualification. Only changes to Data0.com.R2 required qualification. A new file has been produced which contains the database Data0.ymp.R0, which is recommended for qualification as a result of this action. Data0.ymp.R0 will supersede Data0.com.R2 for all Yucca Mountain Project (YMP) activities

Pilot study approach and qualification dossier components

International Nuclear Information System (INIS)

Ammirato, F.; Ashwin, P.

2000-01-01

The aim of the Pilot Project is to evaluate the IAEA Guidelines and methodology for the benefit of IAEA Member States trough a simulation of qualification activities. The Project is based on a real component and available data - NPP Kozloduy unit 5, weld 3. The initial phase is limited to the Qualification dossier. The Project relies on the input from the team members and Member States. Team organization and responsibilities are presented. The components of the Qualification Dossier (technical specification, inspection procedure and preliminary review, qualification procedure) and their current status are also presented. A comparison is done with their qualification programs. The characteristics of performance demonstrations are discussed. The results show that the teamwork has been successful and the IAEA methodology covers all situations. It is expected that the End Project will become 'Benchmark's' for future qualification activities

Seismic qualification of equipment in operating nuclear power plants. Unresolved safety issue A-46, draft report for comment

International Nuclear Information System (INIS)

Chang, T.Y.

1985-08-01

The margin of safety provided in existing nuclear power plant equipment to resist seismically induced loads and perform their intended safety functions may vary considerably, because of significant changes in design criteria and methods for the seismic qualification of equipment over the years. Therefore, the seismic qualification of equipment in operating plants should be reassessed to determine whether requalification is necessary. The objective of technical studies performed under the Task Action Plan A-46 was to establish an explicit set of guidelines and acceptance criteria to judge the adequacy of equipment under seismic loading at all operating plants, in lieu of requiring qualification to the current criteria that are applied to new plants. This report summarizes the work accomplished on USI A-46 by the Nuclear Regulatory Commission staff and its contractors, Idaho National Engineering Laboratory, Southwest Research Institute, Brookhaven National Laboratory, and Lawrence Livermore National Laboratory. In addition, the collection and review of seismic experience data by the Seismic Qualification Utility Group and the review and recommendations of a group of seismic consultants, the Senior Seismic Review Advisory Panel, are presented. Staff assessment of work accomplished under USI A-46 leads to the conclusion that the use of seismic experience data provides the most reasonable alternative to current qualification criteria. Consideration of seismic qualification by use of experience data was a specific task in USI A-46. Several other A-46 tasks serve to support the use of an experience data base

Computer Engineers.

Science.gov (United States)

Moncarz, Roger

2000-01-01

Looks at computer engineers and describes their job, employment outlook, earnings, and training and qualifications. Provides a list of resources related to computer engineering careers and the computer industry. (JOW)

Qualification standard for photovoltaic concentrator modules

Energy Technology Data Exchange (ETDEWEB)

McConnell, R.; Kurtz, S.; Bottenberg, W. R.; Hammond, R.; Jochums, S. W.; McDanal, A. J.; Roubideaux, D.; Whitaker, C.; Wohlgemuth, J.

2000-05-05

The paper describes a proposed qualification standard for photovoltaic concentrator modules. The standard's purpose is to provide stress tests and procedures to identify any component weakness in photovoltaic concentrator modules intended for power generation applications. If no weaknesses are identified during qualification, both the manufacturer and the customer can expect a more reliable product. The qualification test program for the standard includes thermal cycles, humidity-freeze cycles, water spray, off-axis beam damage, hail impact, hot-spot endurance, as well as electrical tests for performance, ground continuity, isolation, wet insulation resistance, and bypass diodes. Because concentrator module performance can not be verified using solar simulator and reference cell procedures suitable for flat-plate modules, the standard specifies an outdoor I-V test analysis allowing a performance comparison before and after a test procedure. Two options to this complex analysis are the use of a reference concentrator module for side-by-side outdoor comparison with modules undergoing various tests and a dark I-V performance check.

Data Qualification Report For: Thermodynamic Data File, DATA0.YMP.R0 For Geochemical Code, EQ3/6 

Energy Technology Data Exchange (ETDEWEB)

P.L. Cloke

2001-10-16

The objective of this work is to evaluate the adequacy of chemical thermodynamic data provided by Lawrence Livermore National Laboratory (LLNL) as DataO.ymp.ROA in response to an input request submitted under AP-3.14Q. This request specified that chemical thermodynamic data available in the file, Data0.com.R2, be updated, improved, and augmented for use in geochemical modeling used in Process Model Reports (PMRs) for Engineered Barrier Systems, Waste Form, Waste Package, Unsaturated Zone, and Near Field Environment, as well as for Performance Assessment. The data are qualified in the temperature range 0 to 100 C. Several Data Tracking Numbers (DTNs) associated with Analysis/Model Reports (AMR) addressing various aspects of the post-closure chemical behavior of the waste package and the Engineered Barrier System that rely on EQ316 outputs to which these data are used as input, are Principal Factor affecting. This qualification activity was accomplished in accordance with the AP-SIII.2Q using the Technical Assessment method. A development plan, TDP-EBS-MD-000044, was prepared in accordance with AP-2.13Q and approved by the Responsible Manager. In addition, a Process Control Evaluation was performed in accordance with AP-SV.1Q. The qualification method, selected in accordance with AP-SIII.2Q, was Technical Assessment. The rationale for this approach is that the data in File Data0.com.R2 are considered Handbook data and therefore do not themselves require qualification. Only changes to Data0.com.R2 required qualification. A new file has been produced which contains the database Data0.ymp.R0, which is recommended for qualification as a result of this action. Data0.ymp.R0 will supersede Data0.com.R2 for all Yucca Mountain Project (YMP) activities.

Perturbing engine performance measurements to determine optimal engine control settings

Science.gov (United States)

Jiang, Li; Lee, Donghoon; Yilmaz, Hakan; Stefanopoulou, Anna

2014-12-30

Methods and systems for optimizing a performance of a vehicle engine are provided. The method includes determining an initial value for a first engine control parameter based on one or more detected operating conditions of the vehicle engine, determining a value of an engine performance variable, and artificially perturbing the determined value of the engine performance variable. The initial value for the first engine control parameter is then adjusted based on the perturbed engine performance variable causing the engine performance variable to approach a target engine performance variable. Operation of the vehicle engine is controlled based on the adjusted initial value for the first engine control parameter. These acts are repeated until the engine performance variable approaches the target engine performance variable.

Post-installed concrete anchors in nuclear power plants: Performance and qualification

International Nuclear Information System (INIS)

Mahrenholtz, Philipp; Eligehausen, Rolf

2015-01-01

Graphical abstract: - Highlights: • Review of qualification and design regulations for anchors in nuclear power plants. • First complete set of nuclear anchor load–displacement data and its evaluation ever. • Demonstration of robust test behavior of a qualified post-installed anchor product. - Abstract: In nuclear power plants (NPPs), post-installed anchors are widely used for structural and non-structural connections to concrete. In many countries, anchor products employed for safety relevant applications have to be approved by the authorities. For the high safety standards in force for NPPs, special requirements have to be met to allow for extreme design situations. This paper presents an experimental test program conducted to evaluate the performance of anchors according to the German Guideline for Anchorages in Nuclear Power Plants and Nuclear Technology Installations (DIBt KKW Leitfaden, 2010). After a brief introduction to anchor behavior and the regulative context, the results of tension and shear tests carried out on undercut anchors are discussed. Robust load capacities and relatively small displacements determined for demanding load and crack cycling tests demonstrated the suitability of anchors qualified according to a state-of-the-art qualification guideline

Nodalization qualification process of the PSBVVER facility for the Cathare2 thermal-hydraulic code

International Nuclear Information System (INIS)

Del Nevo, A.; Araneo, D.; D'Auria, F.; Galassi, G.

2004-01-01

The present document deals with the nodalization qualification process of the PSB-VVER test facility for Cathare2 code. PSB-VVER facility is a 1/300 volume scale model of a VVER-1000, reactor installed at Electrogorsk Research and Engineering Centre in 1998. The version V1.5b of the Cathare2 code has been used. In order to evaluate the nodalization performance, the qualifying procedure set up at the DIMNP of Pisa University (UNIPI) has been applied that foresees two qualification levels: a 'steady state' level and an 'on transient' level. After the steady state behavior check of the nodalization, it has been preformed the on transient qualification the PSB-VVER test 2. It is a 11% equivalent break in Upper Plenum with the actuation of one high pressure injection system, connected to the hot leg of the loop 4, and 4 passive systems (ECCS hydro-accumulators), connected to the outlet plenum and to the inlet chamber of the downcomer. The low-pressure injection system is not available in the test. The goal of this paper is to demonstrate that the first step of the nodalization qualification adopted for the PSB test analyses is achieved and the PSB facility input deck is available and ready to use. The quantitative accuracy of the performed calculation has been evaluated by using the FFT-BM tool developed at the University of Pisa.(author)

Comparative Study of the academic performance between different curricula in Agricultural Engineering

Science.gov (United States)

Vazquez, J. L.; Serrano, A.; Caniego, J.

2012-04-01

Due to the introduction of new degrees on the College of Agricultural Engineering of the Technical University of Madrid adapted to the European Space for Higher Education (Bologna), we have made a comparative study of academic achievement obtained by the students during their first year at the Centre according to different curricula. We used data from 2 curricula leading to the degree in Agricultural Engineering, Curriculumn 74 (6 years and annual structure) and Curriculum 96 modified in 2006 (5 years with quarterly structure) and the new curriculum in grades (4 years semi-structured). It has been used as a data source, the qualifications of new students during the last three years prior to the extinction of the curriculum.The study shows that current rates of academic success or failure and dropout during the first year of college are very similar to those happening 12 years ago, when it was assumed that the preparation of students from high school was much higher than today. Keywords: Academic performance, curricula, Bologna.

APM for a Constellation Intersatellite Link - EM Qualification and Lessons Learned

Science.gov (United States)

Hartel, Frank; Kozilek, Horst

2016-01-01

For an Intersatellite Link (ISL) of a future constellation program, a study phase was initiated by ESA to design a mechanism for Radio Frequency communication. Airbus DS Friedrichshafen (ADSF) proposed a design based on the Antenna Pointing Mechanism (APM) family with modifications that met the stated needs of the constellation. A qualification program was started beginning in September 2015 to verify the launch and thermal loads and the equipment performance (Radio Frequency, Pointing, Microvibration and Magnetic Moment). Technical challenges identified with the Engineering Model will be discussed within this paper.

T25 Qualification of old containers

International Nuclear Information System (INIS)

Hoerning, T.; Kasparek, E.M.; Voelzke, H.

2013-01-01

Radioactive waste for final disposal in the repository Konrad has to be packaged in licensed containers. The qualification of containers is performed according the respective standards and BfS requirements. The latter ones differ for different container types with respect to accident resistance based on the release behavior of the waste. Usually qualification of container types is performed before series production. The qualification of already produced containers (''old containers'') is significantly more complicated. The differences of quality assurance and materials properties of the older containers have to be evaluated. A main tool for this evaluation is the numerical re-calculation of accident scenarios for estimation of the safety margins. The validation of appropriate finite element models is available. Based on these date it might be possible to abandon additional drop tests with the existing old containers to prove the structural integrity.

Inspection procedure and essential parameters in NDT qualification

International Nuclear Information System (INIS)

Sarkimo, M.

2000-06-01

The objective of the inspection qualification is to ensure that applied non-destructive methods (NDT) have the required performance. The approach of the qualification process is systematic and carefully documented and therefore some new requirements can be seen concerning the composition of the documentation. There are also new document types, that only application of the inspection qualification requires. The most important of these is the technical justification, that includes the documented evidences concerning the performance of the inspection system. This publication includes two reports: 'Compilation of the inspection procedure' and 'Essential/influential parameters in NDT qualification'. The former of these discusses the issues to be considered in an inspection procedure especially from the point of view of the mechanised ultrasonic testing. The later report explains the parameters formulated to analyse in the technical justification all aspects of the inspection application. (orig.)

Generic test procedure for the qualification of a nuclear emergency generator

International Nuclear Information System (INIS)

Simonis, J.C.; Bowman, S.W.

1985-01-01

This paper describes the proposed analytical and experimental procedures for the qualification of the standby generators and exciters used in the Emergency Diesel Generator Systems in a nuclear power plant. The components which require qualification are identified through a failure mode analysis of the systems conducted using engineering drawings updated to include all field changes. The qualification of each component includes the margins given in IEEE Std. 323-1974, ''Qualifying Class 1E Equipment for Nuclear Power Generating Stations.'' These margins are combined with the plant specific data to define an enveloping set of environmental parameters. This set of enveloping parameters, plus margin, form the bases for the analysis or test qualification tasks. Proposed qualification of the composite electrical insulation systems used in the generator and exciter on the form or random wound coils is by traceable testing. However, before testing the thermal and radiation degradation data used in the design of the generator and exciter are evaluated to identify if these data are sufficiently traceable to eliminate the need for additional insulation tests. The required tests are guided by applicable standards

A system for personnel qualification of non-destructive testing procedures from testing and and qualification system in Sweden

International Nuclear Information System (INIS)

Kuna, M.; Kubis, S.; Plasek, J.

1999-01-01

The method for qualification of non-destructive testing personnel carrying out inspections by means of ultrasonic and eddy-current tests to inspect cladding in BWR reactor pressure vessel and core shroud lid. Development of procedures tests with real artificial cracks, blind tests. Evaluation of results by the Swedish Qualification Commission. Performance of the tests at Oskarshamn-1

49 CFR 214.343 - Training and qualification, general.

Science.gov (United States)

2010-10-01

... 49 Transportation 4 2010-10-01 2010-10-01 false Training and qualification, general. 214.343... ADMINISTRATION, DEPARTMENT OF TRANSPORTATION RAILROAD WORKPLACE SAFETY Roadway Worker Protection § 214.343 Training and qualification, general. (a) No employer shall assign an employee to perform the duties of a...

QUALIFICATIONS FRAMEWORK DEVELOPMENT AND QUALIFICATIONS RATING IN THE LAND MANAGEMENT SPHERE

Directory of Open Access Journals (Sweden)

A. A. Myrasheva

2014-01-01

Full Text Available The aim of the research is to observe the existing approaches to qualifications framework development in the sphere of land management, cadastres and real estate management, as well as the qualifications framework adaptation to European system. The relevance of the issue is related to the specific professional and institutional problems facing Russian educational establishments engaged in personnel training in the given sphere. The authors demonstrate the qualifications framework development in the land management sector regarding it as a key mechanism of educational mobility and the router for knowledge acquisition and updates. The qualifications framework is referred to as a systematic and structured description of recognized qualifications. The accepted worldwide methodology of organizing the educational process and quality control system is given. The emphasis is on the need to comply the qualifications framework with the Russian State Educational Standards.

Inspector qualification guidelines

International Nuclear Information System (INIS)

Batty, A.C.; Van Binnebeek, J.J.; Ericsson, P.O.; Fisher, J.C.; Geiger, P.; Grandame, M.; Grimes, B.K.; Joode, A. de; Kaufer, B.; Kinoshita, M.; Klonk, H.; Koizumi, H.; Maeda, N.; Maqua, M.; Perez del Moral, C.; Roselli, F.; Warren, T.; Zimmerman, R.

1994-07-01

The OECD Nuclear Energy Agency Committee on Nuclear Regulatory Activities (CNRA) has a Working Group on Inspection Practices (WGIP). The WGIP provides a forum for the exchange of Information and experience on the safety Inspection practices of regulatory authorities In the CNRA member countries. A consistent qualification process and well defined level of training for all Inspectors who participate In the safety Inspections are needed to provide consistent Inspections and reliable Inspection results. The WGIP organized in 1992 a workshop on the conduct of inspections, inspector qualification and training, and shutdown inspections at the Technical Training Center of the US NRC in Chattanooga, Tennessee. In the connection of workshop the WGIP identified a need to develop guidance for inspector qualification which could be used as a model by those who are developing their qualification practices. The inspector qualification journals of US NRC provided a good basis for the work. The following inspector qualification guideline has been developed for guidance of qualification of a new inspector recruited to the regulatory body. This guideline has been developed for helping the supervisors and training officers to give the initial training and familiarization to the duties of a new inspector in a controlled manner. US NRC inspector qualification journals have been used to define the areas of attention. This guideline provides large flexibility for application in different type organizations. Large organizations can develop separate qualification journals for each inspector positions. Small regulatory bodies can develop individual training programmes by defining the necessary training topics on case by case basis. E.g. the guideline can be used to define the qualifications of contracted inspectors used in some countries. The appropriate part would apply. Annex 1 gives two examples how this guideline could be applied

Inspector qualification guidelines

Energy Technology Data Exchange (ETDEWEB)

Batty, A. C.; Van Binnebeek, J. J.; Ericsson, P. O.; Fisher, J. C.; Geiger, P.; Grandame, M.; Grimes, B. K.; Joode, A. de; Kaufer, B.; Kinoshita, M.; Klonk, H.; Koizumi, H.; Maeda, N.; Maqua, M.; Perez del Moral, C.; Roselli, F.; Warren, T.; Zimmerman, R.

1994-07-15

The OECD Nuclear Energy Agency Committee on Nuclear Regulatory Activities (CNRA) has a Working Group on Inspection Practices (WGIP). The WGIP provides a forum for the exchange of Information and experience on the safety Inspection practices of regulatory authorities In the CNRA member countries. A consistent qualification process and well defined level of training for all Inspectors who participate In the safety Inspections are needed to provide consistent Inspections and reliable Inspection results. The WGIP organized in 1992 a workshop on the conduct of inspections, inspector qualification and training, and shutdown inspections at the Technical Training Center of the US NRC in Chattanooga, Tennessee. In the connection of workshop the WGIP identified a need to develop guidance for inspector qualification which could be used as a model by those who are developing their qualification practices. The inspector qualification journals of US NRC provided a good basis for the work. The following inspector qualification guideline has been developed for guidance of qualification of a new inspector recruited to the regulatory body. This guideline has been developed for helping the supervisors and training officers to give the initial training and familiarization to the duties of a new inspector in a controlled manner. US NRC inspector qualification journals have been used to define the areas of attention. This guideline provides large flexibility for application in different type organizations. Large organizations can develop separate qualification journals for each inspector positions. Small regulatory bodies can develop individual training programmes by defining the necessary training topics on case by case basis. E.g. the guideline can be used to define the qualifications of contracted inspectors used in some countries. The appropriate part would apply. Annex 1 gives two examples how this guideline could be applied.

DATA QUALIFICATION REPORT: DATA QUALIFICATION REPORT FOR 1991 1:1200 TOPOGRAPHIC MAPS FOR USE ON THE YUCCA MOUNTAIN PROJECT

International Nuclear Information System (INIS)

Knop, M.F.; Grant, T.A.; Bonisolli, R.W.

2005-01-01

This Data Qualification Report (DQR) is prepared in accordance with the provisions of AP-SIII.2Q, Rev. 0, ICN 3, Qualification of Unqualified Data and the Documentation of Rationale for Accepted Data and Data Qualification Plan for 1991 Topographic Maps 1:1200 Scale for use on the Yucca Mountain Project, DQP-WHS-CI-000001, Rev. 00 (BSC 2002a). This DQR presents an evaluation of a set of 90 topographic sheets at 1:1200 scale (and an associated electronic file) that covers an approximate 18 square mile area surrounding the proposed Yucca Mountain Project repository surface facilities location in Midway Valley, Nevada. These maps, that require qualification, are now being used to determine the physical characteristics of watershed sub-areas, interconnecting channels, and drainage channel cross-sections for hydrologic engineering studies of the north portal pad and vicinity. The result of this effort is to qualify one data tracking number (DTN) containing the electronic version of the mapping data. This DTN is: M09906COV98462.000. Coverage: TOP02FTS. The underlying quality assurance (QA) issue associated with these topographic maps is that the maps were originally designated as not for use in the design of items important to safety, waste isolation, and/or of programmatic importance. The maps were therefore generated outside the U.S. Department of Energy Office of Civilian Radioactive Waste Management (OCRWM) QA program. Based on a comparison with corroborating information, this report concludes that the topographic maps are qualified. The comparison found that the mapping was reasonably accurate when compared with other mapping and survey data within the coverage area of the maps. Relative map accuracy was found to be very good and suitable for the hydrologic engineering studies being considered. Absolute accuracy is good but could not be demonstrated to comply with national map accuracy standards. Point locations that require high absolute accuracy should be

SNF Project Engineering Process Improvement Plan

International Nuclear Information System (INIS)

DESAI, S.P.

2000-01-01

This plan documents the SNF Project activities and plans to support its engineering process. It describes five SNF Project Engineering initiatives: new engineering procedures, qualification cards process; configuration management, engineering self assessments, and integrated schedule for engineering activities

Engineering performance metrics

Science.gov (United States)

Delozier, R.; Snyder, N.

1993-03-01

Implementation of a Total Quality Management (TQM) approach to engineering work required the development of a system of metrics which would serve as a meaningful management tool for evaluating effectiveness in accomplishing project objectives and in achieving improved customer satisfaction. A team effort was chartered with the goal of developing a system of engineering performance metrics which would measure customer satisfaction, quality, cost effectiveness, and timeliness. The approach to developing this system involved normal systems design phases including, conceptual design, detailed design, implementation, and integration. The lessons teamed from this effort will be explored in this paper. These lessons learned may provide a starting point for other large engineering organizations seeking to institute a performance measurement system accomplishing project objectives and in achieving improved customer satisfaction. To facilitate this effort, a team was chartered to assist in the development of the metrics system. This team, consisting of customers and Engineering staff members, was utilized to ensure that the needs and views of the customers were considered in the development of performance measurements. The development of a system of metrics is no different than the development of any type of system. It includes the steps of defining performance measurement requirements, measurement process conceptual design, performance measurement and reporting system detailed design, and system implementation and integration.

Electrical equipment qualification

International Nuclear Information System (INIS)

Farmer, W.S.

1983-01-01

Electrical equipment qualification research programs being carried out by CEA, JAERI, and Sandia Laboratories are discussed. Objectives of the program are: (1) assessment of accident simulation methods for electrical equipment qualification testing; lower coarse (2) evaluation of equipment aging and accelerated aging methods; (3) determine radiation dose spectrum to electrical equipment and assess simulation methods for qualification; (4) identify inadequacies in electrical equipment qualification procedures and standards and potential failure modes; and (5) provide data for verifying and improving standards, rules and regulatory guides

Low-level radioactive waste form qualification testing

International Nuclear Information System (INIS)

Sohal, M.S.; Akers, D.W.

1998-06-01

This report summarizes activities that have already been completed as well as yet to be performed by the Idaho National Engineering and Environmental Laboratory (INEEL) to develop a plan to quantify the behavior of radioactive low-level waste forms. It briefly describes the status of various tasks, including DOE approval of the proposed work, several regulatory and environmental related documents, tests to qualify the waste form, preliminary schedule, and approximate cost. It is anticipated that INEEL and Brookhaven National Laboratory will perform the majority of the tests. For some tests, services of other testing organizations may be used. It should take approximately nine months to provide the final report on the results of tests on a waste form prepared for qualification. It is anticipated that the overall cost of the waste quantifying service is approximately $150,000. The following tests are planned: compression, thermal cycling, irradiation, biodegradation, leaching, immersion, free-standing liquid tests, and full-scale testing

Low-level radioactive waste form qualification testing

Energy Technology Data Exchange (ETDEWEB)

Sohal, M.S.; Akers, D.W.

1998-06-01

This report summarizes activities that have already been completed as well as yet to be performed by the Idaho National Engineering and Environmental Laboratory (INEEL) to develop a plan to quantify the behavior of radioactive low-level waste forms. It briefly describes the status of various tasks, including DOE approval of the proposed work, several regulatory and environmental related documents, tests to qualify the waste form, preliminary schedule, and approximate cost. It is anticipated that INEEL and Brookhaven National Laboratory will perform the majority of the tests. For some tests, services of other testing organizations may be used. It should take approximately nine months to provide the final report on the results of tests on a waste form prepared for qualification. It is anticipated that the overall cost of the waste quantifying service is approximately $150,000. The following tests are planned: compression, thermal cycling, irradiation, biodegradation, leaching, immersion, free-standing liquid tests, and full-scale testing.

Seismic qualification of equipment

International Nuclear Information System (INIS)

Heidebrecht, A.C.; Tso, W.K.

1983-03-01

This report describes the results of an investigation into the seismic qualification of equipment located in CANDU nuclear power plants. It is particularly concerned with the evaluation of current seismic qualification requirements, the development of a suitable methodology for the seismic qualification of safety systems, and the evaluation of seismic qualification analysis and testing procedures

The HTR modular power reactor system. Qualification of fuel elements and materials

International Nuclear Information System (INIS)

Heidenreich, U.; Breitling, H.; Nieder, R.; Ohly, W.; Mittenkuehler, A.; Ragoss, H.; Seehafer, H.J.; Wirtz, K.; Serafin, N.

1989-01-01

For further development of the HTR modular power reactor system (HTR-M-KW), the project activities for 'Qualification of fuel elements and materials' reported here cover the work for specifying the qualifications to be met by metallic and ceramic materials, taking into account the design-based requirements and the engineered safety requirements. The fission product retention data determined for the HTR modular reactor fuel elements could be better confirmed by evaluation of the experiments, and have been verified by various calculation methods for different operating conditions. The qualification of components was verified by strength analyses including a benchmark calculation for specified normal operation and emergencies; the results show a convenient behaviour of the components and their materials. In addition, a fuel element burnup measuring system was designed that applies Cs-137 gamma spectroscopy; its feasibility was checked by appropriate analyses, and qualification work is in progress. The installation of a prototype measurement system is the task for project No. 03 IAT 211. (orig.) [de

Technical evaluation of seismic qualification of safety-related equipment

Energy Technology Data Exchange (ETDEWEB)

Cho, Yang Hui; Park, Heong Gee; Park, Yeong Seok [Univ. of Incheon, Incheon (Korea, Republic of)

1994-04-15

This study is purposed to evaluate the technical acceptability of the procedures and techniques of seismic qualifications which were performed for the YGN 3 and 4 safety-related equipment.This study is also targeted to suggest a systematized technical procedure guide for the effective performance and review of the seismic qualification, which reflects the most up-to-date licensing requirements and state-of the-art.

Effect of Teacher's Qualification on the Performance of Senior Secondary School Physics Students: Implication on Technology in Nigeria

Science.gov (United States)

Owolabi, Olabode Thomas; Adedayo, Julius Olugbenga

2012-01-01

The study examined the effect of teacher's qualification on the performance of Senior Secondary School students in Physics. The purpose was to determine whether the status of the teacher has any impact on the performance of the students in Physics. The survey type of descriptive research design was adopted. The sample for the study consisted of…

29 CFR 1910.410 - Qualifications of dive team.

Science.gov (United States)

2010-07-01

... 29 Labor 5 2010-07-01 2010-07-01 false Qualifications of dive team. 1910.410 Section 1910.410... Requirements § 1910.410 Qualifications of dive team. (a) General. (1) Each dive team member shall have the experience or training necessary to perform assigned tasks in a safe and healthful manner. (2) Each dive team...

Hybrid Qualifications

DEFF Research Database (Denmark)

Against the background of increasing qualification needs there is a growing awareness of the challenge to widen participation in processes of skill formation and competence development. At the same time, the issue of permeability between vocational education and training (VET) and general education...... has turned out as a major focus of European education and training policies and certainly is a crucial principle underlying the European Qualifications Framework (EQF). In this context, «hybrid qualifications» (HQ) may be seen as an interesting approach to tackle these challenges as they serve «two...

THE PROFESSIONAL QUALIFICATION SOLIDARY EXTENSION PROJECT AT ELECTRONICS: TECHNICAL AUXILIAR

Directory of Open Access Journals (Sweden)

Glaucio Lopes Ramos

2009-10-01

Full Text Available This paper has the objective to present the extension course “professional qualification solidary extension project at electronics: technical auxiliar” in the Electrical Engineering course in the University Center of Belo Horizonte, as a professional qualification activity that make possible to young, adults and elderly people from poor communities the social inclusion and an opportunity to improve their access to the labor market. The course is part of extension program of Uni-BH, UniTrabalho e Renda, that is offered since 2006. The responsible for the course are professors and students of the Electrical Engineering course, and an electricity project is also offered. This paper presents the results of an evaluation that is made for the students at the beginning and at the end of the course and showed that the concepts had been assimilated by the students and the expectation of them related to the insertion at labor market is also improved.

Inspection qualification and implementation of ENIQ in Sweden

International Nuclear Information System (INIS)

Zettervall, Tommy

2013-01-01

Many countries are currently considering their approaches to inspection qualification and risk-informed in-service inspection (RI-ISI) and are carefully assessing experience data. In Europe most of the utilities operating nuclear power plants have joined together to form the European Network for Inspection Qualification ENIQ. In practice, qualification can be performed with varying degrees of complexity and cost, varying from capability statement based on existing evidence, through to an extensive qualification consisting of a detailed Technical Justification (TJ) together with open and blind trials on full-scale test blocks. An Inspection Qualification is an investigation and demonstration, which confirm that an inspection system has the ability to solve its specific tasks. The qualification is a Quality Assurance of an inspection system based on documents and practical trials. A reliable inspection system, based on a reliable qualification and correct prerequisites, will reduce total costs for Licensees and increase the credibility of the inspection result. To get such inspection system, which could be valid for many years, it's of necessity to fulfil all included parts in the process. It begins with the Technical Specification from Licensee, where input data and requirements about the actual component are specified. To get an inspection system that could live over time, the Technical Justification is of importance. Finally the test blocks and used simulation techniques play an important part of the final result, and these test blocks together with TJ form the basis for qualification body's decision. (author)

Qualification of high heat flux components: application to target elements of W7-X divertor

International Nuclear Information System (INIS)

Missirlian, M; Durocher, A; Grosman, A; Schlosser, J; Boscary, J; Escourbiac, F; Cismondi, F

2007-01-01

The development of actively cooled plasma-facing components (PFC) represents one of fusion's most challenging engineering efforts. In this frame, a high-quality bonding between the refractory armour and the heat sink is essential to ensure the heat removal capability and the thermal performances of PFC. Experience gained during manufacturing of Tore Supra actively cooled PFC led to the establishment of a qualification methodology and provided a large experience of acceptance criteria using an active infrared thermography (systeme d'acquisition de traitement infra-rouge, SATIR). This paper presents the application of this qualification process to the W7-X pre-series components, with the objective of assessing and defining workable acceptance criteria that enable reliable predictions of performance at the nominal heat flux requirements in W7-X. Finally, to check the reliability of the non-destructive examination (NDE) method by transient infrared thermography, the newly defined acceptance criteria were applied to W7-X pre-series target elements (batch no. 3). The SATIR results, benchmarked with HHF tests performed on the GLADIS ion beam facility were discussed to assess the ability to detect critical defects at the interface between tiles and heat sink

Australian Qualifications Framework Lower-Level Qualifications: Pathways to Where for Young People?

Science.gov (United States)

Stanwick, John

2005-01-01

This study investigates where certificate I and II qualifications lead young people aged 15-24 years in terms of employment and further study. A prime motivation for young people undertaking these qualifications is to facilitate transition into the labour market. These qualifications are aimed at developing basic vocational skills or preparatory…

Professional Identification for Biomedical Engineers

Science.gov (United States)

Long, Francis M.

1973-01-01

Discusses four methods of professional identification in biomedical engineering including registration, certification, accreditation, and possible membership qualification of the societies. Indicates that the destiny of the biomedical engineer may be under the control of a new profession, neither the medical nor the engineering. (CC)

Space qualification of an experimental two-phase flow thermal management system

International Nuclear Information System (INIS)

Koonmen, J.P.; Carswell, L.C.; Kvansnak, M.A.

1991-01-01

The Weapons Laboratory will launch a space experiment in March 1991 to investigate the effects of extended microgravity on two-phase (liquid/vapor) flow. The qualification process for the experimental flight system hardware differs significantly from the process used for complex, high cost, long life space systems. Some development, qualification, and acceptance tests normally included in the test program of an operational space system were omitted because of the low program cost and low consequence of experiment failure. Key environment and functional qualification tests were performed, however, in an effort to reduce the risk of failure inherent in any space mission. The environmental qualification program included short duration vacuum chamber tests, reduced gravity missions onboard a National Aeronautics and Space Administration (NASA) test aircraft, and a complete series of shock and vibration tests. The functional qualification program centered on thermal-hydraulic system performance tests and a complete check-out of the unique telemetry system used to retrieve the experimental data from the payload. The test program also contains a number of acceptance and prelaunch validation tests to be performed as final verification of payloads readiness for spaceflight

Occupational scope and qualification of environment experts in public administration. Final report. Berufsfeld- und Qualifikationsanalyse fuer Umweltfachleute in der Oeffentlichen Verwaltung. Abschlussbericht

Energy Technology Data Exchange (ETDEWEB)

Brater, M; Hemmer, C; Maurus, A; Munz, C; Schluchter,

1991-12-01

The publication presents the three parts of the original report in one volume. The parts refewing to occupational qualifications consistently differentiate between occupation all specific qualification standards and those of a non-specific nature. Environmental protection is defined to be based on pollution control as a matter of engineering, pollution abatement as a matter of planning and regulatory activities, and the integrated version of the two strategies. Experts in public administration specialising in environmental protection are to be trained as experts in the following sub-areas environmental planning (innovation and strategy planning); design planning (engineering aspects); environmental law (impact statements, expert opinions, special knowledge of environmental media); enforcement of the law, licensing procedure, monitoring and supervision (efficiency evaluation); public relations (information, consultancy, education). The report presents job descriptions, qualification standards, occupational scopes and prospects for every type of qualification and education. (HSCH).

A manual for pyrotechnic design, development and qualification

Science.gov (United States)

Bement, Laurence J.; Schimmel, Morry L.

1995-01-01

Although pyrotechnic devices have been singularly responsible for the success of many of the critical mechanical functions in aerospace programs for over 30 years, ground and in-flight failures continue to occur. Subsequent investigations reveal that little or no quantitative information is available on measuring the effects on performance of system variables or on determining functional margins. Pyrotechnics are considered to be readily available and, therefore, can be managed by any subsystem in which they are applied, such as structure, propulsion, electric power, or life support. The primary purpose of this manual is to alter the concept that the use of pyrotechnics is an art and refute 'justifications' that applications do not need to be understood by providing information on pyrotechnic design, development, and qualification on an engineering basis. Included are approaches to demonstrate functional reliability with less than 10 units, how to manage pyrotechnic-unique requirements, and methods to assure that the system is properly assembled and will perform the required tasks.

Rover Low Gain Antenna Qualification for Deep Space Thermal Environments

Science.gov (United States)

Ramesham, Rajeshuni; Amaro, Luis R.; Brown, Paula R.; Usiskin, Robert; Prater, Jack L.

2013-01-01

A method to qualify the Rover Low Gain Antenna (RLGA) for use during the Mars Science Laboratory (MSL) mission has been devised. The RLGA antenna must survive all ground operations, plus the nominal 670 Martian sol mission that includes the summer and winter seasons of the Mars thermal environment. This qualification effort was performed to verify that the RLGA design, its bonding, and packaging processes are adequate. The qualification test was designed to demonstrate a survival life of three times more than all expected ground testing, plus a nominal 670 Martian sol missions. Baseline RF tests and a visual inspection were performed on the RLGA hardware before the start of the qualification test. Functional intermittent RF tests were performed during thermal chamber breaks over the course of the complete qualification test. For the return loss measurements, the RLGA antenna was moved to a test area. A vector network analyzer was calibrated over the operational frequency range of the antenna. For the RLGA, a simple return loss measurement was performed. A total of 2,010 (3 670 or 3 times mission thermal cycles) thermal cycles was performed. Visual inspection of the RLGA hardware did not show any anomalies due to the thermal cycling. The return loss measurement results of the RLGA antenna after the PQV (Package Qualification and Verification) test did not show any anomalies. The antenna pattern data taken before and after the PQV test at the uplink and downlink frequencies were unchanged. Therefore, the developed design of RLGA is qualified for a long-duration MSL mission.

Relationship Between Teachers\\' Qualification And Students ...

African Journals Online (AJOL)

It has been observed that students\\' performance in technical subjects is very poor. Coupled with this problem is that of lack of qualified technical teachers. This study determines the relationship between teachers\\' qualification and students\\' performance in technical subjects in selected schools in northern Nigeria.

Qualification of non-destructive examination for belgian nuclear reactor pressure vessel inspection

International Nuclear Information System (INIS)

Couplet, D.; Francoise, T.

2001-01-01

In Service Inspection (ISI) participates to the assessment of Nuclear Reactor Pressure Vessel Integrity. The performance of Non Destructive Examination (NDE) techniques must be demonstrated according to predefined objectives. The qualification process is essential to trust the reliability of the information provided by NDE. In Belgian Nuclear Power Plants, the qualification was conducted through a collaboration between the vendor and a technical group from the Electricity Utility. The important facts of this qualification will be presented: - the detailed definition of the inspection and qualifications objectives, based on a combination of the ASME code and the European Methodology for Qualification; - the systematic verification of the NDE performance and limitations, for each ISI objective, through an adequate combination of tests on blocks and technical justification; - the continuous improvement of the NDE procedure; - the feedback and the lessons learnt from site experience; - the necessary multi-disciplinary approach (NDE, degradation mechanisms, structural integrity)

Implementation plans for the Korean certified tumor registrar qualification system.

Science.gov (United States)

Boo, Yoo-Kyung; Lim, Hyun-Sook; Won, Young-Joo

2014-01-01

Cancer registration data is used to understand the nation's cancer burden, and to provide significant baseline data for cancer control efforts, as well as, research on cancer incidence, mortality, survival, and prevalence. A system that approves, assesses, and manages the qualification of specialists, responsible for performing cancer registration, has not been developed in Korea. This study presents ways to implement a certification system designed for the qualification of tumor registrars in Korea. Requirements for implementing a certified tumor registrar qualification system were determined by reviewing the system for establishing qualifications in Korea and the American qualification system via the National Cancer Registrars Association (NCRA). Moreover, a survey was conducted on Korean medical records administrators, who had taken the U.S. Certified Tumor Registrar (CTR) examination, in order to review their opinions regarding these requirements. This study verified the feasibility of a qualification examination based on the opinions of CTR specialists by determining the following: items, and the associated ratings, of the qualifications necessary to register individuals as certified tumor registrars in a private qualification system; status of human resources required for the examination or training processes; plans regarding the organization needed for management, and operation of qualifications, examination standards, subject areas, examination methods, examination qualifications, or education and training programs. The implementation of a certified tumor registrar qualification system will lead to enhanced job competency for specialists and a qualitative improvement of cancer registration data. It will also reliably foster human resources that will lay the groundwork needed to establish scientific and reasonable national cancer management policies.

Use of reliability engineering in development and manufacturing of metal parts

International Nuclear Information System (INIS)

Khan, A.; Iqbal, M.A.; Asif, M.

2005-01-01

The reliability engineering predicts modes of failures and weak links before the system is built instead of failure case study. The reliability engineering analysis will help in the manufacturing economy, assembly accuracy and qualification by testing, leading to production of metal parts in an aerospace industry. This methodology will also minimize the performance constraints in any requirement for the application of metal components in aerospace systems. The reliability engineering predicts the life of the parts under loading conditions whether dynamic or static. Reliability predictions can help engineers in making decisions about design of components, materials selection and qualification under applied stress levels. Two methods of reliability prediction i.e. Part Stress Analysis and Part Count have been used in this study. In this paper we will discuss how these two methods can be used to measure reliability of a system during development phases, which includes the measuring effect of environmental and operational variables. The equations are used to measure the reliability of each type of component, as well as, integration for measuring system applied for the reliability analysis. (author)

Environmental Testing of the NEXT PM1R Ion Engine

Science.gov (United States)

Snyder, John S.; Anderson, John R.; VanNoord, Jonathan L.; Soulas, George C.

2007-01-01

The NEXT propulsion system is an advanced ion propulsion system presently under development that is oriented towards robotic exploration of the solar system using solar electric power. The subsystem includes an ion engine, power processing unit, feed system components, and thruster gimbal. The Prototype Model engine PM1 was subjected to qualification-level environmental testing in 2006 to demonstrate compatibility with environments representative of anticipated mission requirements. Although the testing was largely successful, several issues were identified including the fragmentation of potting cement on the discharge and neutralizer cathode heater terminations during vibration which led to abbreviated thermal testing, and generation of particulate contamination from manufacturing processes and engine materials. The engine was reworked to address most of these findings, renamed PM1R, and the environmental test sequence was repeated. Thruster functional testing was performed before and after the vibration and thermal-vacuum tests. Random vibration testing, conducted with the thruster mated to the breadboard gimbal, was executed at 10.0 Grms for 2 min in each of three axes. Thermal-vacuum testing included three thermal cycles from 120 to 215 C with hot engine re-starts. Thruster performance was nominal throughout the test program, with minor variations in a few engine operating parameters likely caused by facility effects. There were no significant changes in engine performance as characterized by engine operating parameters, ion optics performance measurements, and beam current density measurements, indicating no significant changes to the hardware as a result of the environmental testing. The NEXT PM1R engine and the breadboard gimbal were found to be well-designed against environmental requirements based on the results reported herein. The redesigned cathode heater terminations successfully survived the vibration environments. Based on the results of this test

Reaction Qualifications Revisited

DEFF Research Database (Denmark)

Lippert-Rasmussen, Kasper

2009-01-01

  When, in a competitive sphere, people are selected on the basis of qualifications only, their chances of acquiring positions of advantage may seem to depend entirely upon their abilities, not discriminatory bias. However, if reaction qualifications - i.e. characteristics which contribute...... to a person's effectiveness by causing a favourable reaction in customers, co-workers etc. (for short: recipients) - are involved, this assumption is false. Building on work by Wertheimer, Mason, and Miller, this paper proposes an account of the reaction qualifications that count, from the point of view...... of merit. Specifically, it preserves symmetry between negative evaluations of antimeritocratic bases of selection and negative evaluations of qualifications rooted in comparable antimeritocratic reactions. So if employers should not select among applicants on the basis of their (the employers') racial...

Environmental Testing of the NEXT PM1 Ion Engine

Science.gov (United States)

Synder, John S.; Anderson, John R.; VanNoord, Jonathan L.; Soulas, George C.

2008-01-01

The NEXT propulsion system is an advanced ion propulsion system presently under development that is oriented towards robotic exploration of the solar system using solar electric power. The Prototype Model engine PM1 was subjected to qualification-level environmental testing to demonstrate compatibility with environments representative of anticipated mission requirements. Random vibration testing, conducted with the thruster mated to the breadboard gimbal, was executed at 10.0 Grms for 2 minutes in each of three axes. Thermal-vacuum testing included a deep cold soak of the engine to temperatures of -168 C and thermal cycling from -120 to 203 C. Although the testing was largely successful, several issues were identified including the fragmentation of potting cement on the discharge and neutralizer cathode heater terminations during vibration which led to abbreviated thermal testing, and generation of particulate contamination from manufacturing processes and engine materials. Thruster performance was nominal throughout the test program, with minor variations in some engine operating parameters likely caused by facility effects. In general, the NEXT PM1 engine and the breadboard gimbal were found to be well-designed against environmental requirements based on the results reported herein. After resolution of the findings from this test program the hardware environmental qualification program can proceed with confidence.

SRNL PHASE 1 Assessment Of The WTP Waste Qualification Program

International Nuclear Information System (INIS)

Peeler, D.; Hansen, E.; Herman, C.; Marra, S.; Wilmarth, B.

2012-01-01

The Hanford Tank Waste Treatment and Immobilization Plant (WTP) Project is currently transitioning its emphasis from an engineering design and construction phase toward facility completion, start-up and commissioning. With this transition, the WTP Project has initiated more detailed assessments of the requirements that must be met during the actual processing of the Hanford Site tank waste. One particular area of interest is the waste qualification program. In general, the waste qualification program involves testing and analysis to demonstrate compliance with waste acceptance criteria, determine waste processability, and demonstrate laboratory-scale unit operations to support WTP operations. The testing and analysis are driven by data quality objectives (DQO) requirements necessary for meeting waste acceptance criteria for transfer of high-level wastes from the tank farms to the WTP, and for ensuring waste processability including proper glass formulations during processing within the WTP complex. Given the successful implementation of similar waste qualification efforts at the Savannah River Site (SRS) which were based on critical technical support and guidance from the Savannah River National Laboratory (SRNL), WTP requested subject matter experts (SMEs) from SRNL to support a technology exchange with respect to waste qualification programs in which a critical review of the WTP program could be initiated and lessons learned could be shared. The technology exchange was held on July 18-20, 2011 in Richland, Washington, and was the initial step in a multi-phased approach to support development and implementation of a successful waste qualification program at the WTP. The 3-day workshop was hosted by WTP with representatives from the Tank Operations Contractor (TOC) and SRNL in attendance as well as representatives from the US DOE Office of River Protection (ORP) and the Defense Nuclear Facility Safety Board (DNFSB) Site Representative office. The purpose of the

Progress on EPRI electrical equipment qualification research

International Nuclear Information System (INIS)

Sliter, G.E.

1983-01-01

The objective of EPRI's electrical equipment qualification research program is to provide technical assistance to utilities in meeting nuclear plant safety requirements in a manner consistent with the state of the art. This paper reports progress on several research projects including: radiation effects studies, which compile data on degradation of organic materials in electrical equipment exposed to operational and accident radiation doses; the Equipment Qualification Data Bank, which is a remotely accessible computer system for disseminating qualification information on in-plant equipment, seismic data, and materials data; an aging/seismic correlation program, which is providing test data showing that, in many cases, age degradation has a negligibly small effect on the performance of electrical components under seismic excitation; a review of condition monitoring techniques, which has identified surveillance methods for measuring key performance parameters that have the potential for predicting remaining equipment life; and large-scale hydrogen burn equipment response tests, which are providing data to assess the ability of equipment to remain functional during and after hydrogen burning in postulated degraded core accidents

Passive autocatalytic recombiner process features and new status of international qualification

International Nuclear Information System (INIS)

Eckardt, Bernd A.; Losch, Norbert

2010-01-01

New results of International PAR-Severe Accidents Qualification in frame of EC/IRSN Core Melt Program PHEBUS (with real molten core) are presented. Example Results: AREVA PAR Design: Best performance very fast start-up • highest efficiency absolutely constant hydrogen depletion rates. Others: Some industrial competitors failed. This enveloping real severe accident tests represents the new international PAR qualification standard and finalized the PAR qualification successfully. The design features supports PAR Dual function

Techniques and tools for software qualification in KNICS

International Nuclear Information System (INIS)

Cha, Kyung H.; Lee, Yeong J.; Cheon, Se W.; Kim, Jang Y.; Lee, Jang S.; Kwon, Kee C.

2004-01-01

This paper describes techniques and tools for qualifying safety software in Korea Nuclear Instrumentation and Control System (KNICS). Safety software are developed and applied for a Reactor Protection System (RPS), an Engineered Safety Features and Component Control System (ESF-CCS), and a safety Programmable Logic Controller (PLC) in the KNICS. Requirements and design specifications of safety software are written by both natural language and formal specification languages. Statechart is used for formal specification of software of the ESF-CCS and the safety PLC while NuSCR is used for formal specification of them of the RPS. pSET (POSCON Software Engineering Tool) as a software development tool has been developed and utilized for the IEC61131-3 based PLC programming. The qualification of the safety software consists of software verification and validation (V and V) through software life cycle, software safety analysis, and software configuration management, software quality assurance, and COTS (Commercial-Off-The-Shelf) dedication. The criteria and requirements for qualifying the safety software have been established with them in Software Review Plan (SRP)/Branch Technical Positions (BTP)-14, IEEE Std. 7-4.3.2-1998, NUREG/CR-6463, IEEE Std. 1012-1998, and so on. Figure 1 summarizes qualification techniques and tools for the safety software

Background information for NDT qualification of Finnish disposal canisters of spent fuel

International Nuclear Information System (INIS)

Sarkimo, M.; Pitkaenen, J.

2013-12-01

This report presents a review to basic concepts, which are applied in the qualification of non-destructive testing (NDT) techniques. The qualification systems developed and used in some countries are briefly described in the beginning of the report. Anyway the report mainly discusses the qualification practices applied in the Finnish nuclear industry. The Finnish Radiation and Nuclear Safety Authority (STUK) in the YVL Guide 3.8 define the Finnish qualification approach applied for the in-service inspections. The principles presented in this document follow the views of the international organisations: Nuclear Regulator Working Group (NRWG) and European Network for Inspection and Qualification (ENIQ). For the practical qualification work a national guideline is established using so called SP-documents that include specific rules and instructions for execution of qualifications in accordance with YVL Guide 3.8 principles. Altogether the Finnish qualification system can be seen very well to follow the European (ENIQ) methodology. The report discusses several qualification terms and documents. Thus the normally necessary tasks and parts of a qualification are described. The qualification can be seen as a project that includes several tasks, which will be performed by different parties. Enough resources and time should be reserved for the planning and control of a qualification project to ensure its fluent progress. Some tasks are discussed in the report taking into account the situation in the qualification cases that are seen to be linked to the inspections of disposal canisters of spent fuel. (orig.)

Background information for NDT qualification of Finnish disposal canisters of spent fuel

Energy Technology Data Exchange (ETDEWEB)

Sarkimo, M. [VTT Technical Research Centre of Finland, Espoo (Finland); Pitkaenen, J.

2013-12-15

This report presents a review to basic concepts, which are applied in the qualification of non-destructive testing (NDT) techniques. The qualification systems developed and used in some countries are briefly described in the beginning of the report. Anyway the report mainly discusses the qualification practices applied in the Finnish nuclear industry. The Finnish Radiation and Nuclear Safety Authority (STUK) in the YVL Guide 3.8 define the Finnish qualification approach applied for the in-service inspections. The principles presented in this document follow the views of the international organisations: Nuclear Regulator Working Group (NRWG) and European Network for Inspection and Qualification (ENIQ). For the practical qualification work a national guideline is established using so called SP-documents that include specific rules and instructions for execution of qualifications in accordance with YVL Guide 3.8 principles. Altogether the Finnish qualification system can be seen very well to follow the European (ENIQ) methodology. The report discusses several qualification terms and documents. Thus the normally necessary tasks and parts of a qualification are described. The qualification can be seen as a project that includes several tasks, which will be performed by different parties. Enough resources and time should be reserved for the planning and control of a qualification project to ensure its fluent progress. Some tasks are discussed in the report taking into account the situation in the qualification cases that are seen to be linked to the inspections of disposal canisters of spent fuel. (orig.)

Synergistic Development, Test, and Qualification Approaches for the Ares I and V Launch Vehicles

Science.gov (United States)

Cockrell, Charles E.; Taylor, James L.; Patterson, Alan; Stephens, Samuel E.; Tyson, Richard W.; Hueter, Uwe

2009-01-01

The U.S. National Aeronautics and Space Administration is designing and developing the Ares I and Ares V launch vehicles for access to the International Space Station (ISS) and human exploration of the Moon. The Ares I consists of a first stage reusable five-segment solid rocket booster, a upper stage using a J-2X engine derived from heritage experience (Saturn and Space Shuttle External Tank programs), and the Orion crew exploration vehicle (CEV). The Ares V is designed to minimize the development and overall life-cycle costs by leveraging off of the Ares I design. The Ares V consists of two boosters, a core stage, an earth departure stage (EDS), and a shroud. The core stage and EDS use LH2/LO2 propellants, metallic propellant tanks, and composite dry structures. The core stage has six RS-68B upgraded Delta IV engines while the EDS uses a J-2X engine for second stage ascent and trans-lunar injection (TLI) burn. System and propulsion tests and qualification approaches for Ares V elements are being considered as follow-on extensions of the Ares I development program. Following Ares I IOC, testing will be conducted to verify the J-2X engine's orbital restart and TLI burn capability. The Ares I upper stage operation will be demonstrated through integrated stage development and acceptance testing. The EDS will undergo similar development and acceptance testing with additional testing to verify aspects of cryogenic propellant management, operation of sub-systems in a space simulation environment, and orbital re-start of the main propulsion system. RS-68B certification testing will be conducted along with integrated core stage development and acceptance testing. Structural testing of the Ares V EDS and core stage propellant tanks will be conducted similar to the Ares I upper stage. The structural qualification testing may be accomplished with separate propellant tank test articles. Structural development and qualification testing of the dry structure will be pursued as

Environmental/dynamic mechanical equipment qualification and dynamic electrical equipment qualification program (EDQP)

International Nuclear Information System (INIS)

Hunter, J.A.

1984-01-01

Equipment qualification research is being conducted to investigate acceptable criteria, requirements, and methodologies for the dynamic (including seismic) and environmental qualification of mechanical equipment and for the dynamic (including seismic) qualification of electrical equipment. The program is organized into three elements: (1) General Research, (2) Environmental Research, and (3) Dynamic Research. This paper presents the highlights of the results to date in these three elements of the program

AP-102/104 Retrieval control system qualification test procedure

International Nuclear Information System (INIS)

RIECK, C.A.

1999-01-01

This Qualification Test Procedure documents the results of the qualification testing that was performed on the Project W-211, ''Initial Tank Retrieval Systems,'' retrieval control system (RCS) for tanks 241-AP-102 and 241-AP-104. The results confirm that the RCS has been programmed correctly and that the two related hardware enclosures have been assembled in accordance with the design documents

Return of IEEE Std 627 and its Value to Equipment Qualification Programs

International Nuclear Information System (INIS)

Horvath, D.A.

2012-01-01

IEEE Std 627 ''Design Qualification of Safety Systems Equipment Used in Nuclear Power Generating Stations'' was issued to more generically establish qualification requirements in the form of a high level umbrella document. Efforts on this standard began in late 1975 at the request of the IEEE Nuclear Standards Management Board. In 1977 a joint ASME/IEEE agreement established responsibility for qualification and quality assurance standards preparation. ASME accepted responsibility for Quality Assurance and IEEE for qualification. In accordance with that agreement, IEEE completed the generic qualification standard in 1980. This document provided high level approaches, criteria, guidance, and principles for qualification of both electrical and mechanical equipment that at that time appeared in no other industry standard. IEEE Std 627-1980 was later reaffirmed in 1996. In 1986, ASME's Board on Nuclear Codes and Standards directed its Committee on Qualification of Mechanical Equipment (QME) to develop a standard for qualifying mechanical equipment. This task was completed in several parts during the time frame from 1992 to 1994. Partly in response to this activity, IEEE Std 627 was withdrawn in 2002. Later although withdrawn, it was found that IEEE Std 627 was continuing to be used and referenced by many entities both in the US and other countries including in ASME's QME-1-2002 ''Qualification of Active Mechanical Equipment Used in Nuclear Power Plants'', US NRC's NUREG-0800 Standard Review Plan Section 3.11, at least one reactor vendor's Design Certification Document (DCD), several international licensing documents, and elsewhere. As a result, in 2007, the IEEE Standards Board authorized Working Group 2.10 of Subcommittee 2 (Qualification) of the Power and Energy Society's Nuclear Power Engineering Committee to resurrect and update IEEE Std 627-1980 (Reaff 1996). The result was the culmination IEEE Std 627 in 2010. This paper will report on the eight improvements made

Qualification of NDE personnel in the nuclear industry

International Nuclear Information System (INIS)

Epps, T.N.

1984-01-01

There has been evidence of ineffective programs for certifying nondestructive examination (NDE) personnel who conduct periodic inservice examinations in nuclear power plants under ASME Section XI Code requirements. This was brought to the attention of a group from the electric utility industry, the Electric Power Research Institute (EPRI), some NDE consultants and representatives from the American Society of Mechanical Engineers (ASME) by the Nuclear Regulatory Commission (NRC) in a May, 1982 meeting in Bethesda, Maryland. One problem pointed out by the NRC was the lack of a clear definition of qualification requirements for certification of NDE personnel who conduct ASME Section XI Inservice Inspection work in nuclear power plants. The NRC requested that the nuclear industry resolve this problem by formulating definitive qualification requirements for personnel certification that could be made an industry requirement. In June, 1982 the EPRI NDE Subcommittee held a general meeting for utility representatives to discuss the results of the May, 1982 meeting to develop a plan for industry response to the issue. The consensus was that an Ad Hoc Committee of utility representatives be convened to develop a document outlining qualification requirements for vertification of NDE personnel. The Ad Hoc Committee was formally convened on September 29, 1982

Radiological Control Technician: Standardized technician Qualification Standard

International Nuclear Information System (INIS)

1992-10-01

The Qualification Standard states and defines the knowledge and skill requirements necessary for successful completion of the Radiological Control Technician Training Program. The standard is divided into three phases: Phase I concerns RCT Academic training. There are 13 lessons associated with the core academics program and 19 lessons associated with the site academics program. The staff member should sign the appropriate blocks upon successful completion of the examination for that lesson or group of lessons. In addition, facility specific lesson plans may be added to meet the knowledge requirements in the Job Performance Measures (JPM) of the practical program. Phase II concerns RCT core/site practical (JPMs) training. There are thirteen generic tasks associated with the core practical program. Both the trainer/evaluator and student should sign the appropriate block upon successful completion of the JPM. In addition, facility specific tasks may be added or generic tasks deleted based on the results of the facility job evaluation. Phase III concerns the oral examination board successful completion of the oral examination board is documented by the signature of the chairperson of the board. Upon completion of all of the standardized technician qualification requirements, final qualification is verified by the student and the manager of the Radiological Control Department and acknowledged by signatures on the qualification standard. The completed Qualification Standard shall be maintained as an official training record

Engineering and science education for nuclear power

International Nuclear Information System (INIS)

1986-01-01

The Guidebook contains detailed information on curricula which would provide the professional technical education qualifications which have been established for nuclear power programme personnel. The core of the Guidebook consists of model curricula in engineering and science, including relevant practical work. Curricula are provided for specialization, undergraduate, and postgraduate programmes in nuclear-oriented mechanical, chemical, electrical, and electronics engineering, as well as nuclear engineering and radiation health physics. Basic nuclear science and engineering laboratory work is presented together with a list of basic experiments and the nuclear equipment needed to perform them. Useful measures for implementing and improving engineering and science education and training capabilities for nuclear power personnel are presented. Valuable information on the national experiences of IAEA Member States in engineering and science education for nuclear power, as well as examples of such education from various Member States, have been included

Assessment of job-related educational qualifications for nuclear power plant operators

International Nuclear Information System (INIS)

Saari, L.M.; Melber, B.D.; White, A.S.

1985-04-01

This report identifies job-related educational qualifications for the nuclear power plant licensed operator positions of reactor operator (RO), senior reactor operator (SRO), and shift supervisor (SS). The extent to which college engineering curriculum covers job-related academic knowledge was assessed. The approach used was to have subject matter experts in the field of general and nuclear engineering curriculum systematically compare college engineering program content to specific academic knowledge identified by a job analysis as necessary for licensed operators. In addition, these experts made judgments concerning levels of formal engineering education necessary for application of knowledge on the job, based on job samples from a job analysis of activities under selected normal and emergency operating sequences

REGULATION OF NATIONAL QUALIFICATIONS SYSTEMS

Directory of Open Access Journals (Sweden)

Anna A. Muravyeva

2014-01-01

Full Text Available The paper looks into the diverse aspects of qualifications system regulation, designed for balancing the supply and demand in the labor and educational service markets. Both the objects and mechanisms of such regulation are described. Special attention is given to institutions, involved in regulation of qualifications, and their jurisdiction. Another emphasis is on the industry-related regulation of qualifications which proved to be effective both on the national and European level. Such structures were first established on the national levels to regulate the qualifications and ensure their comparability and compatibility, given the economic globalization and growing labor and academic mobility. The author points out the role of the ministries of education and labor in maintaining a steady qualifications system, and outlines the positive experience of Great Britain using the industry councils for continuing development of qualifications system.

The comparison of System 1000 analysis and type testing for neoprene gasket environmental qualification

International Nuclear Information System (INIS)

Park, Kyung Heum; Kim, Jong Seok; Jeong, Sun Chul; Jang, Kyung Nam; Hwang, Sung Phil

2010-01-01

The typical environmental qualification is to ensure that equipment will operate on demand to meet system performance requirements during normal and abnormal service conditions. There are four environmental qualification methods, type testing, operating experience, analysis and combined method. Generally, the American EQ do not contain the mechanical equipment like pumps and valves in their EQ equipment list because their EQ standard 10CFR50.49 limits EQ equipment as electrical equipment. On the other hand, Canadian EQ contain the mechanical equipment like pumps and valves in their EQ components list, Canadians usually call American 'equipment' as 'components', because their EQ standard CSA N290.13-05 do not limits EQ equipment as electrical equipment. System 1000 program is typical Canadian EQ analysis method using mathematical modeling and comparison with established engineering information and manufacturers' data. Most of Canadian nuclear power utilities like NB Power, Hydro Quebec and OPG use the System 1000 program to evaluate the design life for their EQ components. To qualify a pump, I had to list all the non-metallic parts in the pump and found there are lots of gaskets made by neoprene material. I tried to qualify these neoprene gaskets by analysis using System 1000 program and by type testing. In this paper, I'd like to introduce the qualification results of neoprene gasket both type testing and analysis using System 1000 program

Sludge Washing And Demonstration Of The DWPF Flowsheet In The SRNL Shielded Cells For Sludge Batch 8 Qualification

Energy Technology Data Exchange (ETDEWEB)

Pareizs, J. M.; Crawford, C. L.

2013-04-26

The current Waste Solidification Engineering (WSE) practice is to prepare sludge batches in Tank 51 by transferring sludge from other tanks to Tank 51. Tank 51 sludge is washed and transferred to Tank 40, the current Defense Waste Processing Facility (DWPF) feed tank. Prior to transfer of Tank 51 to Tank 40, the Savannah River National Laboratory (SRNL) typically simulates the Tank Farm and DWPF processes using a Tank 51 sample (referred to as the qualification sample). WSE requested the SRNL to perform characterization on a Sludge Batch 8 (SB8) sample and demonstrate the DWPF flowsheet in the SRNL shielded cells for SB8 as the final qualification process required prior to SB8 transfer from Tank 51 to Tank 40. A 3-L sample from Tank 51 (the SB8 qualification sample; Tank Farm sample HTF-51-12-80) was received by SRNL on September 20, 2012. The as-received sample was characterized prior to being washed. The washed material was further characterized and used as the material for the DWPF process simulation including a Sludge Receipt and Adjustment Tank (SRAT) cycle, a Slurry Mix Evaporator (SME) cycle, and glass fabrication and chemical durability measurements.

Qualification test on class 1E charger and inverter in nuclear power plant

International Nuclear Information System (INIS)

Li Mingcheng; Lin Jian; Fu Mingxing; Xu Benfu; Ma Peifeng

2014-01-01

The qualification approach for class lE electrical equipment was introduced, based on IEC, IEEE and RCC-E standards and technical documents. Combined with a lot of practical experience, the qualification scheme for class lE charger and inverter was developed. The component evaluation, performance and stress test, EMC test, seismic test and software qualification for the equipment were analyzed in detail. (authors)

Participant outcomes, perceptions, and experiences in the Internationally Educated Engineers Qualification Program, University of Manitoba: An exploratory study

Science.gov (United States)

Friesen, Marcia R.

Immigration, economic, and regulatory trends in Canada have challenged all professions to examine the processes by which immigrant professionals (international graduates) achieve professional licensure and meaningful employment in Canada. The Internationally Educated Engineers Qualification Program (IEEQ) at the University of Manitoba was developed as an alternate pathway to integrate international engineering graduates into the engineering profession in Manitoba. However, universities have the neither mandate nor the historical practice to facilitate licensure for immigrant professionals and, thus, the knowledge base for program development and delivery is predominantly experiential. This study was developed to address the void in the knowledge base and support the program's ongoing development by conducting a critical, exploratory, participant-oriented evaluation of the IEEQ Program for both formative and summative purposes. The research questions focussed on how the IEEQ participants perceived and described their experiences in the IEEQ Program, and how the participants' outcomes in the IEEQ Program compared to international engineering graduates pursuing other licensing pathways. The study was built on an interpretivist theoretical approach that supported a primarily qualitative methodology with selected quantitative elements. Data collection was grounded in focus group interviews, written questionnaires, student reports, and program records for data collection, with inductive data analysis for qualitative data and descriptive statistics for quantitative data. The findings yielded rich understandings of participants' experiences in the IEEQ Program, their outcomes relative to international engineering graduates (IEGs) pursuing other licensing pathways, and their perceptions of their own adaptation to the Canadian engineering profession. Specifically, the study suggests that foreign credentials recognition processes have tended to focus on the recognition and

Qualification and certification of nondestructive testing personnel. Vol. 1

Energy Technology Data Exchange (ETDEWEB)

Aly, E A [Quality Assurance Department, national Center for Nuclear Safety and Radiation Control, Atomic Energy Authority, Cairo, (Egypt)

1996-03-01

Nondestructive testing and inspection are functions in achieving the goals of quality and efficiency at an acceptable cost. All quality assurance systems necessitate that engineers, technicians and craftsmen are able to demonstrate that they have the required level of knowledge and skill. This applies particularly to nondestructive testing (NDT) and inspection. The paper presented highlights most important national and international standards and guidelines addressing training, qualification and certification of NDT personnel.

Qualification and certification of nondestructive testing personnel. Vol. 1

International Nuclear Information System (INIS)

Aly, E.A.

1996-01-01

Nondestructive testing and inspection are functions in achieving the goals of quality and efficiency at an acceptable cost. All quality assurance systems necessitate that engineers, technicians and craftsmen are able to demonstrate that they have the required level of knowledge and skill. This applies particularly to nondestructive testing (NDT) and inspection. The paper presented highlights most important national and international standards and guidelines addressing training, qualification and certification of NDT personnel

Software qualification in safety applications

International Nuclear Information System (INIS)

Lawrence, J.D.

2000-01-01

The developers of safety-critical instrumentation and control systems must qualify the design of the components used, including the software in the embedded computer systems, in order to ensure that the component can be trusted to perform its safety function under the full range of operating conditions. There are well known ways to qualify analog systems using the facts that: (1) they are built from standard modules with known properties; (2) design documents are available and described in a well understood language; (3) the performance of the component is constrained by physics; and (4) physics models exist to predict the performance. These properties are not generally available for qualifying software, and one must fall back on extensive testing and qualification of the design process. Neither of these is completely satisfactory. The research reported here is exploring an alternative approach that is intended to permit qualification for an important subset of instrumentation software. The research goal is to determine if a combination of static analysis and limited testing can be used to qualify a class of simple, but practical, computer-based instrumentation components for safety application. These components are of roughly the complexity of a motion detector alarm controller. This goal is accomplished by identifying design constraints that enable meaningful analysis and testing. Once such design constraints are identified, digital systems can be designed to allow for analysis and testing, or existing systems may be tested for conformance to the design constraints as a first step in a qualification process. This will considerably reduce the cost and monetary risk involved in qualifying commercial components for safety-critical service

The status and challenges of Industrial Engineering in South Africa

Directory of Open Access Journals (Sweden)

Schutte, Cornelius S. L.

2016-05-01

Full Text Available The industrial engineering discipline in South Africa is examined by introducing the context of the discipline and by revisiting its history. The drivers influencing the context and future of industrial engineering in South Africa are also considered, and the discipline is analysed in terms of the following aspects: university qualifications, employment in industry sectors, race and gender profiles, use and competence in industry, and income profiles. The analysis is based on a recent survey sent to practising industrial engineers, on membership data from the Southern African Institute for Industrial Engineering (SAIIE, and on two internal SAIIE investigations. The study concludes that the success of transformation, particularly in terms of race, has been limited. The results also indicate that there are an almost equal number of black and white industrial engineers, yet the majority of black industrial engineers have technical qualifications, while the majority of white industrial engineers have academic qualifications. The results indicate that this limits the use of black industrial engineers in industry and, consequently, the success of their careers. This in turn means that there are fewer black role models to attract young black students to the discipline. Some preliminary opportunities to unlock the increased transformation of the profession are identified.

AGR-1 Data Qualification Interim Report

International Nuclear Information System (INIS)

Abbott, Machael

2009-01-01

Projects for the very-high-temperature reactor (VHTR) program provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR Program has established the NGNP Data Management and Analysis System (NDMAS) to ensure that VHTR data are (1) qualified for use, (2) stored in a readily accessible electronic form, and (3) analyzed to extract useful results. This document focuses on the first NDMAS objective. It describes the data streams associated with the first Advanced Gas Reactor (AGR-1) experiment, the processing of these data within NDMAS, and reports the interim FY09 qualification status of the AGR-1 data to date. Data qualification activities within NDMAS for specific types of data are determined by the data qualification category, which is assigned by the data generator, and include: (1) capture testing, to confirm that the data stored within NDMAS are identical to the raw data supplied, (2) accuracy testing, to confirm that the data are an accurate representation of the system or object being measured, and (3) documentation that the data were collected under an NQA-1 or equivalent QA program. The interim qualification status of the following four data streams is reported in this document: (1) fuel fabrication data, (2) fuel irradiation data, (3) fission product monitoring system (FPMS) data, and (4) Advanced Test Reactor (ATR) operating conditions data. A final report giving the NDMAS qualification status of all AGR-1 data (including cycle 145A) is planned for February 2010

Nuclear Criticality Safety Organization qualification program. Revision 4

International Nuclear Information System (INIS)

Carroll, K.J.; Taylor, R.G.; Worley, C.A.

1997-01-01

The Nuclear Criticality Safety Organization (NCSO) is committed to developing and maintaining a staff of highly qualified personnel to meet the current and anticipated needs in Nuclear Criticality Safety (NCS) at the Oak Ridge Y-12 Plant. This document defines the Qualification Program to address the NCSO technical and managerial qualification as required by the Y-12 Training Implementation Matrix (TIM). It is implemented through a combination of LMES plant-wide training courses and professional nuclear criticality safety training provided within the organization. This Qualification Program is applicable to technical and managerial NCSO personnel, including temporary personnel, sub-contractors and/or LMES employees on loan to the NCSO, who perform the NCS tasks or serve NCS-related positions as defined in sections 5 and 6 of this program

Enhanced Massive Visualization of Engines Performance

International Nuclear Information System (INIS)

Rostand, N D; Eglantine, H; Jerôme, L

2012-01-01

Today, we are witnessing an increasing complexity of transport in order to deal with requirements of safety, security, reliability and efficiency. Such transport is generally equipped with drive systems; it is nevertheless for engine manufacturers to overcome the performance requirements of energy efficiency throughout their operations. To this end, this article proposes a performance monitoring solution for a large fleet of engines in operation. It uses a pre-calibrated physical model developed by the engine manufacturer regarding the performance objectives as reference. The physical model is firstly decomposed into critical performance modules, and is secondly updated on current observations extracted at specific predefined operating conditions in order to derive residual errors status of each engine tested. Through a process of standardization of those contextual differences remaining, the solution offers a synthesis mapping to visualize the evolution of performance of each engine throughout its operations. This article describes the theoretical methodology of implementation mainly based on universal mathematical foundations, and vindicates the interests of its industrialization in the light of the proactive findings.

Qualifications manual for Inspection and Enforcement personnel. Volume I. Detailed data sheets

International Nuclear Information System (INIS)

Bartley, H.J.; Heyer, F.H.K.; Schwartz, E.G.; Harrison, O.J.; Krass, I.W.; Welsh, D.M.

1978-06-01

This document is the General Research Corporation (GRC) final report on Task I Job/Position Qualifications Statements for the Headquarters and regional position of NRC/IE. It reflects the results of upgrading, expanding, and reformating the preliminary Task I report. To accomplish this, GRC made a thorough examination of all data developed during Task I, Task II (Career Fields), Task III (Training Evaluation), and Task IV (Hiring Qualifications), to include NRC/IE comments and management decisions received. The reformated Job/Position Qualifications Statements resulting from this effort (Appendix A) identify three job qualifications categories for each position--performance, attributes, and knowledge. Two formats are provided: a summarized one for manpower management in Volume I and a detailed one for career and training management in Volume II. In addition to recommending approval of the job/position qualifications, GRC proposes their use in conjunction with the hiring qualifications in the Task IV report to update NRC/IE job descriptions

Earthquake experience and seismic qualification by indirect methods in nuclear installations

International Nuclear Information System (INIS)

2003-01-01

In recent years, many operational nuclear power plants around the world have conducted seismic re-evaluation programmes either as part of a review of seismic hazards or to comply with best international nuclear safety practices. In this connection, Member States have called on the IAEA to carry out several seismic review missions at their plants, primarily those of WWER and RBMK design. One of the critical safety issues that arose during these missions was that of seismic qualification (determination of fitness for service) of already installed plant distribution systems, equipment and components. The qualification of new components, equipment and distribution systems cannot be replicated for equipment that is already installed and operational in plants, as this process is neither feasible nor appropriate. For this reason, seismic safety experts have developed new procedures for the qualification of installed equipment: these procedures seek to demonstrate that installed equipment, through a process of comparison with new equipment, is apt for service. However, these procedures require large sets of criteria and qualification databases and call for the use of engineering judgement and experience, all of which open the door to wide margins of interpretation. In order to guarantee a sound technical basis for the qualification of in-plant equipment, currently applied to 70% to 80% of all plant equipment, the regulatory review of this type of qualification process calls for a detailed assessment of the technical procedures applied. Such an assessment is the first step towards eliminating the risk of large differences in qualification results between different plants, operators and countries, and guaranteeing the reliability of seismic re-evaluation programmes. Bearing this in mind, in 1999, the IAEA convened a seminar and technical meeting on seismic qualification under the auspices of the IAEA Technical Co-operation programme. Altogether 66 senior experts attended the

46 CFR 54.20-5 - Welding qualification tests and production testing (modifies UW-26, UW-28, UW-29, UW-47, and UW-48).

Science.gov (United States)

2010-10-01

... 46 Shipping 2 2010-10-01 2010-10-01 false Welding qualification tests and production testing... OF HOMELAND SECURITY (CONTINUED) MARINE ENGINEERING PRESSURE VESSELS Fabrication by Welding § 54.20-5 Welding qualification tests and production testing (modifies UW-26, UW-28, UW-29, UW-47, and UW-48). (a...

Qualification of RETRAN for simulator applications

International Nuclear Information System (INIS)

Harrison, J.F.

1988-01-01

The use of full-scope control room replica simulators increased substantially following the accident at Three Mile Island Unit 2. The technical capability required to represent severe events has been included, in varying degrees, in most simulators purchased since the TMI-2 accident. The ability of the instructor to create a large variety of combinations of malfunctions has also greatly expanded. The nuclear industry has developed a standard which establishes the minimum functional requirements for full-scope nuclear control room simulators used for operator training. This standard, ANSI/ANS-3.5, was first issued in 1981 and was reissued in 1985. A method for performing simulator qualification with best estimate analytical data has been proposed in EPRI NP-4243, Analytic Simulator Qualification Methodology. The idea presented there is to choose a set of transients which drive the simulator into all the system conditions (dynamic states) likely to be encountered during operator training. The key observable parameters for each state are compared to analyses performed with the best estimate analytical model The closeness of the comparison determines the fidelity of the simulator. The approach described in EPRI NP-4243 has been adapted for evaluating RETRAN's capability for use in simulator qualification. RETRAN analyses which compare the RETRAN results to plant or test facility data are evaluated with respect to the simulator test matrix documented in EPRI NP-4243

Qualification test for ITER HCCR-TBS mockups with high heat flux test facility

Energy Technology Data Exchange (ETDEWEB)

Kim, Suk-Kwon, E-mail: skkim93@kaeri.re.kr [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Park, Seong Dae; Jin, Hyung Gon; Lee, Eo Hwak; Yoon, Jae-Sung; Lee, Dong Won [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Cho, Seungyon [National Fusion Research Institute, Daejeon (Korea, Republic of)

2016-11-01

Highlights: • The test mockups for ITER HCCR (Helium Cooled Ceramic Reflector) TBS (Test Blanket System) in Korea were designed and fabricated. • A thermo-hydraulic analysis was performed using a high heat flux test facility by using electron beam. • The plan for qualification tests was developed to evaluate the thermo-hydraulic efficiency in accordance with the requirements of the ITER Organization. - Abstract: The test mockups for ITER HCCR (Helium Cooled Ceramic Reflector) TBS (Test Blanket System) in Korea were designed and fabricated, and an integrity and thermo-hydraulic performance test should be completed under the same or similar operation conditions of ITER. The test plan for a thermo-hydraulic analysis was developed by using a high heat flux test facility, called the Korean heat load test facility by using electron beam (KoHLT-EB). This facility is utilized for a qualification test of the plasma facing component (PFC) for the ITER first wall and DEMO divertor, and for the thermo-hydraulic experiments. In this work, KoHLT-EB will be used for the plan of the performance qualification test of the ITER HCCR-TBS mockups. This qualification tests should be performed to evaluate the thermo-hydraulic efficiency in accordance with the requirements of the ITER Organization (IO), which describe the specifications and qualifications of the heat flux test facility and test procedure for ITER PFC.

Seismic qualification tests of fans of the NPP of Laguna Verde U-1 and U-2

International Nuclear Information System (INIS)

Jarvio C, G.; Garcia H, E. E.; Arguelles F, R.; Vela H, A.; Naranjo U, J. L.

2013-10-01

This work presents the results of the seismic qualification tests applied to the fans that will be installed in the control panels of the three divisions of the diesel generators of the nuclear power plant (NPP) of Laguna Verde, Unit-1 and Unit-2. This seismic qualification process of the fans was carried out using two specimens that were tested in the seismic table (vibrating) of the Engineering Institute of Universidad Nacional Autonoma de Mexico (UNAM), in accordance with the requirements of the standard IEEE 344-1975, to satisfy the established requirements of seismic qualification in the technical specifications and normative documents required by the nuclear standards, in order to demonstrate its application in the diesel generators Divisions I, II and III of the NPP. The seismic qualification tests were developed on specimens that were retired of the NPP of Laguna Verde recently with a service life of 7.75 years. (Author)

IEEE standard for design qualification of safety systems equipment used in nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1980-01-01

This standard is written to serve as a general standard for qualification of all types of safety systems equipment, mechanical and instrumentation as well as electrical. It also establishes principles and procedures to be followed in preparing specific safety systems equipment standards. Guidance for qualifying specific safety systems equipment may be found in various specific equipment qualification standards that are now available or are being prepared. It is required that safety systems equipment in nuclear power generating stations meet or exceed its performance requirements throughout its installed life. This is accomplished by a disciplined program of design qualification and quality assurance of design, production, installation, maintenance and surveillance. This standard is for the design qualification section of the program only. Design qualification is intended to demonstrate the capability of the equipment design to perform its safety function(s) over the expected range of normal, abnormal, design basis event, post design basis event, and in-service test conditions. Inherent to design qualification is the requirement for demonstration, within limitations afforded by established technical state-of-the-art, that in-service aging throughout the qualified life established for the equipment will not degrade safety systems equipment from its original design condition to the point where it cannot perform its required safety function(s), upon demand. The above requirement reflects the primary role of design qualification to provide reasonable assurance that design- and age-related common failure modes will not occur during performance of safety function(s) under postulated service conditions

On the evolution of the regulatory guidance for seismic qualification of electric and active mechanical equipment for nuclear power plants

International Nuclear Information System (INIS)

Ng, Ching Hang; Chen, Pei-Ying

2009-01-01

All electric and active mechanical equipment important to safety for nuclear power plants must be seismically qualified by testing, analysis, or combined analysis and testing. The general requirements for seismic qualification of electric and active mechanical equipment in nuclear power plants are delineated in Appendix S, 'Earthquake Engineering Criteria for Nuclear Power Plants,' to Title 10, Part 50, 'Domestic Licensing of Production and Utilization Facilities,' of the Code of Federal Regulations (10 CFR Part 50), item 52.47(20) of 10 CFR 52.47, 'Contents of Applications; Technical Information,' and Appendix A, 'Seismic and Geologic Siting Criteria for Nuclear Power Plants,' to 10 CFR Part 100, 'Reactor Site Criteria.' The United States Nuclear Regulatory Commission (NRC) issued Revision 2 of Regulatory Guide (RG) 1.100, 'Seismic Qualification of Electric and Mechanical for Nuclear Power Plants' in 1988, which endorsed, with restrictions, exceptions, and clarifications, Institute of Electrical and Electronics Engineers (IEEE) Standard 344-1987 'IEEE Recommended Practice for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations,' for use in seismic qualification of both electric and mechanical equipment. In 2008, the staff at the NRC drafted Revision 3 of RG 1.100 to endorse, with restrictions, exceptions, and clarifications, the IEEE Std 344-2004 and the American Society of Mechanical Engineers (ASME) QME-1-2007 'Qualification of Active Mechanical Equipment Used in Nuclear Power Plants.' IEEE Std 344-2004 was an update of Std 344-1987 and ASME QME-1-2007 was an update of QME-1-2002. The major changes in IEEE Std 344-2004 and ASME QME-1-2007 include the update and expansion of criteria and procedures describing the use of experience data as a method for seismic qualification of Class 1E electric equipment (including I and C components) as well as active mechanical equipment. In this paper, the staff will compare the draft Revision 3 to

Changing nature of equipment and parts qualification

International Nuclear Information System (INIS)

Bucci, R.M.

1988-01-01

Ideally, the original supplier of a piece of nuclear safety-related equipment has performed a qualification program and will continue to support that equipment throughout the lifetime of the nuclear power plants in which in equipment is installed. The supplier's nuclear quality assurance program will be maintained and he will continue to offer all necessary replacement parts. These parts will be identical to the original parts, certified to the original purchase order requirements, and the parts will be offered at competitive prices. Due to the changing nature of the nuclear plant equipment market, however, one or more of those ideal features are frequently unavailable when safety-related replacement equipment or parts are required. Thus, the process of equipment and parts qualification has had to adjust in order to ensure obtaining qualified replacements when needed. This paper presents some new directions taken in the qualification of replacement equipment and parts to meet changes in the marketplace

Prechamber Compression-Ignition Engine Performance

Science.gov (United States)

Moore, Charles S; Collins, John H , Jr

1938-01-01

Single-cylinder compression-ignition engine tests were made to investigate the performance characteristics of prechamber type of cylinder head. Certain fundamental variables influencing engine performance -- clearance distribution, size, shape, and direction of the passage connecting the cylinder and prechamber, shape of prechamber, cylinder clearance, compression ratio, and boosting -- were independently tested. Results of motoring and of power tests, including several typical indicator cards, are presented.

Improving engineering performance by utilizing process indicators

International Nuclear Information System (INIS)

Roberts, T.E.

1992-01-01

The purpose of the work discussed in this paper was to develop engineering performance indicators used to facilitate improvement to the technical quality, cost-effectiveness, and delivery of engineering products and service. This work was specifically tailored for engineering support products and service associated with operating Florida Power and Light Company (FP and L) nuclear plants. The engineering process for the development of plant change packages was reviewed to identify critical in-process activities. Because each engineering project usually deals with a specific component or plant system, the different tasks are usually technically unique and of varying magnitudes. Although each engineering product may employ different analytical techniques or industry code requirements, several activities in documenting the engineering design process are generic. The quality of performance in these activities can be monitored analogously to the steps in a manufacturing process. This concept builds quality concepts into the package in lieu of inspecting package quality at the end of the process. The work has resulted in a valuable self-assessment tool that serves as a basis for engineering process improvements. The indicators are published in a semi-yearly performance report for FP and L contractors as well as FP and L in-house engineering work. Contracts have been set up to base fees on meeting targets established for the performance report. The ability to meet performance targets continues to improve

5 CFR 302.403 - Qualifications for promotion.

Science.gov (United States)

2010-01-01

... 5 Administrative Personnel 1 2010-01-01 2010-01-01 false Qualifications for promotion. 302.403... EMPLOYMENT IN THE EXCEPTED SERVICE Selection and Appointment; Reappointment; and Qualifications for Promotion § 302.403 Qualifications for promotion. In determining qualifications for promotion with respect to an...

5 CFR 330.208 - Qualification requirements.

Science.gov (United States)

2010-01-01

... perform the duties and responsibilities of the position. (c) The sex of an individual may not be... qualified for a position if he or she: (1) Meets OPM-established or approved qualification standards and requirements for the position, including any minimum educational requirements, and any selection placement...

Manual on training, qualification and certification of quality assurance personnel

International Nuclear Information System (INIS)

1986-01-01

The Manual is applicable to those participants in a nuclear power project who are associated with establishment and implementation of the various quality assurance (QA) programmes during the life cycle of the project. It provides examples of typical QA functions to be undertaken and the associated qualification requirements, training programmes, training techniques and methods of certification of personnel implementing these functions. The necessary qualification and training requirements and practices for QA personnel are dependent primarily on the functions or activities to be performed. The two main functions of the QA unit noted previously as (a) ensuring QA programme establishment and execution and (b) verifying that activities have been correctly performed have been found in practice to require different qualifications and training of personnel. Therefore, for the purpose of this Manual the QA personnel may be classified in two groups who perform: QA programmatic and evaluation functions; Inspection and test functions. These titles do not necessarily represent separate or individual organizational groups or units and may be composed of one or of several different organizations

Environmental qualification program for new designs

International Nuclear Information System (INIS)

Doerffer, K.

2007-01-01

Qualification of nuclear power plant equipment and components important to safety (ITS) is an integral part of the design process. The qualification methodology differs based on the severity of service conditions (operational and ambient), to which the ITS equipment is exposed. In Canada, the licensing requirements for environmental qualification for new designs are governed by the Canadian Standard Association (CSA) standard, N290.13-2005 titled 'Environmental Qualification of Equipment for CANDU Nuclear Power Plants' and the pre-consultation draft, 'Requirements for Design of Nuclear Power Plants'(DRD), issued for trial use by the Canadian Nuclear Safety Commission (CNSC) in March 2005. This paper will describe AECL's current Environmental Qualification program developed to comply with the above licensing requirements as applied to new designs. The focus will be given to qualification of ITS systems structures and components (SSC) to harsh conditions occurring due to the Design Basis Accidents (DBA). (author)

Development of nuclear equipment qualification technology

Energy Technology Data Exchange (ETDEWEB)

Choi, Heon O; Kim, Wu Hyun; Kim, Jin Wuk; Kim, Jeong Hyun; Lee, Jeong Kyu; Kim, Yong Han; Jeong, Hang Keun [Korea Institute of Machinery and Materials, Taejon (Korea)

1999-03-01

In order to enhance testing and evaluation technologies, which is one of the main works of the Chanwon branch of KIMM(Korea Institute of Machinery and Materials), in addition to the present work scope of the testing and evaluation in the industrial facilities such as petroleum and chemical, plants, the qualification technologies of the equipments important to safety used in the key industrial facilities such as nuclear power plants should be localized: Equipments for testing and evaluation is to be set up and the related technologies must be developed. In the first year of this study, of vibration aging qualification technologies of equipments important to safety used in nuclear power plants have been performed. (author). 27 refs., 81 figs., 17 tabs.

EADS-ST's Latest Bipropellant 10N Thruster and 400 N Engine: The Fully European Solution

Science.gov (United States)

Fick, M.; Dreer, T.; Gotzig, U.; Schulte, G.; Bachmann, J.; Lagier, F.; Benoit, E.

2004-10-01

Increasing restrictions, complications and bureaucratic hurdles for obtaining export licenses from the US government for American components to be used on certain projects and for certain launch sites or end customers, required the development of new or upgraded European flow control valves to guarantee an independent and unrestricted marketing of EADS-ST's orbital propulsion products to commercial customers worldwide. The development and qualification of the European flow control valves for EADS-ST's 10 N bipropellant thruster and 400 N bipropellant engine is highlighted, together with verification tests and the qualification programs at engine level. The 400 N engine under qualification with the new valves is an enhanced version with an increased area ratio of the nozzle.

5 CFR 319.302 - Individual qualifications.

Science.gov (United States)

2010-01-01

... 5 Administrative Personnel 1 2010-01-01 2010-01-01 false Individual qualifications. 319.302... Individual qualifications. Agency heads are delegated authority to approve the qualifications of individuals appointed to SL and ST positions. The agency head must determine that the individual meets the...

Radiation effect on rocket engine performance

Science.gov (United States)

Chiu, Huei-Huang; Kross, K. W.; Krebsbach, A. N.

1990-01-01

Critical problem areas involving the effect of radiation on the combustion of bipropellants are addressed by formulating a universal scaling law in combination with a radiation-enhanced vaporization combustion model. Numerical algorithms are developed and data pertaining to the Variable Thrust Engine (VTE) and the Space Shuttle Main Engine (SSME) are used to conduct parametric sensitivity studies to predict the principal intercoupling effects of radiation. The analysis reveals that low-enthalpy engines, such as the VTE, are vulnerable to a substantial performance setback due to radiative loss, whereas the performance of high-enthalpy engines such as the SSME are hardly affected over a broad range of engine operation. Combustion enhancement by radiative heating of the propellant has a significant impact on propellants with high absorptivity.

Qualification of Indigenously Developed Special Coatings for Aero-Engine Components

OpenAIRE

V. Sambasiva Rao; T. Rangaraju; V. Unnikrishnan

1999-01-01

The demand for higher performance and reliability of aero-engiaes necessitates its components to worksatisfactorily under severe operating conditions. The durability of various components in these environmentis often enhanced by applying suitable coatings. The development of new materials/processing methods andalso various coatings to protect the components have been driven by the ever-increasing severity of theaero-engine internal environment. While the selection of a coating is dictated by ...

VHDL basics applied design by SIPAC qualification system

International Nuclear Information System (INIS)

Park, In Ha; Mun, Da Cheol; Lee, Gwang Yeob

2005-12-01

This book has six chapters, which are about Flowrian of SIPAC qualification system including internet CAD system and remote server service, logic circuit on design and qualification of device such as gate circuit, multiplex and decoder, order logic circuit with D type flip-flop design and qualification and Rom and RAM's design and qualification, finite state machine such as odd checker, sequence detector, test clock generator and traffic light controller, design and qualification about data path, design of application circuit. It has two appendixes on install and the way to use SIPAC qualification system and remote service for SIPAC qualification system.

Fuel Combustion and Engine Performance | Transportation Research | NREL

Science.gov (United States)

Fuel Combustion and Engine Performance Fuel Combustion and Engine Performance Photo of a gasoline emissions in advanced engine technologies. Photo by Dennis Schroeder, NREL NREL's combustion research and combustion and engine research activities include: Developing experimental and simulation research platforms

Prognostics-based qualification of high-power white LEDs using Lévy process approach

Science.gov (United States)

Yung, Kam-Chuen; Sun, Bo; Jiang, Xiaopeng

2017-01-01

Due to their versatility in a variety of applications and the growing market demand, high-power white light-emitting diodes (LEDs) have attracted considerable attention. Reliability qualification testing is an essential part of the product development process to ensure the reliability of a new LED product before its release. However, the widely used IES-TM-21 method does not provide comprehensive reliability information. For more accurate and effective qualification, this paper presents a novel method based on prognostics techniques. Prognostics is an engineering technology predicting the future reliability or determining the remaining useful lifetime (RUL) of a product by assessing the extent of deviation or degradation from its expected normal operating conditions. A Lévy subordinator of a mixed Gamma and compound Poisson process is used to describe the actual degradation process of LEDs characterized by random sporadic small jumps of degradation degree, and the reliability function is derived for qualification with different distribution forms of jump sizes. The IES LM-80 test results reported by different LED vendors are used to develop and validate the qualification methodology. This study will be helpful for LED manufacturers to reduce the total test time and cost required to qualify the reliability of an LED product.

NRC Information No. 89-23: Environmental qualification of Litton-Veam CIR series electrical connectors

International Nuclear Information System (INIS)

Rossi, C.E.

1992-01-01

Litton-Veam CIR series multi-pin electrical connectors are used in core exit thermocouple (CET) and reactor vessel level monitoring (RVLM) systems supplied to numerous plants by Combustion Engineering, Inc., and are used in other applications in at least three additional plants. A proprietary qualification test report has been used to document environmental qualification of the connectors for loss of coolant accident (LOCA) conditions in the CE-supplied systems. During LOCA testing, the connector face seal gasket was completely degraded and elastomeric inserts interacted with simulated containment spray solution which leaked into the connector. Insulation resistances near 1,000 ohms were measured. CE has performed analyses to show that resultant errors are acceptable in CE-supplied CET and RVLM system thermocouple circuits. However, the moisture ingress and resultant low insulation resistances are not acceptable for heater circuits in the RVLM. For that application, CE developed two remedies; one is a clamp, and the other is a new connector design. CE has advised that one of these remedies has been used for all of the RVLM heater circuits. Unmodified CIR connectors are believed to be still in use in other applications

Fiber Laser Component Testing for Space Qualification Protocol Development

Science.gov (United States)

Falvey, S.; Buelow, M.; Nelson, B.; Starcher, Y.; Thienel, L.; Rhodes, C.; Tull, Jackson; Drape, T.; Westfall, C.

A test protocol for the space qualifying of Ytterbium-doped diode-pumped fiber laser (DPFL) components was developed under the Bright Light effort, sponsored by AFRL/VSE. A literature search was performed and summarized in an AMOS 2005 conference paper that formed the building blocks for the development of the test protocol. The test protocol was developed from the experience of the Bright Light team, the information in the literature search, and the results of a study of the Telcordia standards. Based on this protocol developed, test procedures and acceptance criteria for a series of vibration, thermal/vacuum, and radiation exposure tests were developed for selected fiber laser components. Northrop Grumman led the effort in vibration and thermal testing of these components at the Aerospace Engineering Facility on Kirtland Air Force Base, NM. The results of the tests conducted have been evaluated. This paper discusses the vibration and thermal testing that was executed to validate the test protocol. The lessons learned will aid in future assessments and definition of space qualification protocols. Components representative of major items within a Ytterbium-doped diode-pumped fiber laser were selected for testing; including fibers, isolators, combiners, fiber Bragg gratings, and laser diodes. Selection of the components was based on guidelines to test multiple models of typical fiber laser components. A goal of the effort was to test two models (i.e. different manufacturers) of each type of article selected, representing different technologies for the same type of device. The test articles did not include subsystems or systems. These components and parts may not be available commercial-off-the-shelf (COTS), and, in fact, many are custom articles, or newly developed by the manufacturer. The primary goal for this effort is a completed taxonomy that lists all relevant laser components, modules, subsystems, and interfaces, and cites the documentation for space

AZ-101 Mixer Pump Test Qualification Test Procedures (QTP)

International Nuclear Information System (INIS)

THOMAS, W.K.

2000-01-01

Describes the Qualification test procedure for the AZ-101 Mixer Pump Data Acquisition System (DAS). The purpose of this Qualification Test Procedure (QTP) is to confirm that the AZ-101 Mixer Pump System has been properly programmed and hardware configured correctly. This QTP will test the software setpoints for the alarms and also check the wiring configuration from the SIMcart to the HMI. An Acceptance Test Procedure (ATP), similar to this QTP will be performed to test field devices and connections from the field

Application of Microprocessor-Based Equipment in Nuclear Power Plants - Technical Basis for a Qualification Methodology

International Nuclear Information System (INIS)

Korsah, K.

2001-01-01

This document (1) summarizes the most significant findings of the ''Qualification of Advanced Instrumentation and Control (I and C) Systems'' program initiated by the Nuclear Regulatory Commission (NRC); (2) documents a comparative analysis of U.S. and European qualification standards; and (3) provides recommendations for enhancing regulatory guidance for environmental qualification of microprocessor-based safety-related systems. Safety-related I and C system upgrades of present-day nuclear power plants, as well as I and C systems of Advanced Light-Water Reactors (ALWRs), are expected to make increasing use of microprocessor-based technology. The Nuclear Regulatory Commission (NRC) recognized that the use of such technology may pose environmental qualification challenges different from current, analog-based I and C systems. Hence, it initiated the ''Qualification of Advanced Instrumentation and Control Systems'' program. The objectives of this confirmatory research project are to (1) identify any unique environmental-stress-related failure modes posed by digital technologies and their potential impact on the safety systems and (2) develop the technical basis for regulatory guidance using these findings. Previous findings from this study have been documented in several technical reports. This final report in the series documents a comparative analysis of two environmental qualification standards--Institute of Electrical and Electronics Engineers (IEEE) Std 323-1983 and International Electrotechnical Commission (IEC) 60780 (1998)--and provides recommendations for environmental qualification of microprocessor-based systems based on this analysis as well as on the findings documented in the previous reports. The two standards were chosen for this analysis because IEEE 323 is the standard used in the U.S. for the qualification of safety-related equipment in nuclear power plants, and IEC 60780 is its European counterpart. In addition, the IEC document was published in

Prevalence of GMC performance assessments in the United Kingdom: a retrospective cohort analysis by country of medical qualification

OpenAIRE

Mehdizadeh, L.; Potts, H. W. W.; Sturrock, A.; Dacre, J.

2017-01-01

Background The demographics of doctors working in the UK are changing. The United Kingdom (UK) has voted to leave the European Union (EU) and there is heightened political discourse around the world about the impact of migration on healthcare services. Previous work suggests that foreign trained doctors perform worse than UK graduates in postgraduate medical examinations. We analysed the prevalence by country of primary medical qualification of doctors who were required to take an assessment ...

WTP Waste Feed Qualification: Glass Fabrication Unit Operation Testing Report

Energy Technology Data Exchange (ETDEWEB)

Stone, M. E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL). Hanford Missions Programs; Newell, J. D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL). Process Technology Programs; Johnson, F. C. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL). Engineering Process Development; Edwards, T. B. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL). Engineering Process Development

2016-07-14

The waste feed qualification program is being developed to protect the Hanford Tank Waste Treatment and Immobilization Plant (WTP) design, safety basis, and technical basis by assuring waste acceptance requirements are met for each staged waste feed campaign prior to transfer from the Tank Operations Contractor to the feed receipt vessels inside the Pretreatment Facility. The Waste Feed Qualification Program Plan describes the three components of waste feed qualification: 1. Demonstrate compliance with the waste acceptance criteria 2. Determine waste processability 3. Test unit operations at laboratory scale. The glass fabrication unit operation is the final step in the process demonstration portion of the waste feed qualification process. This unit operation generally consists of combining each of the waste feed streams (high-level waste (HLW) and low-activity waste (LAW)) with Glass Forming Chemicals (GFCs), fabricating glass coupons, performing chemical composition analysis before and after glass fabrication, measuring hydrogen generation rate either before or after glass former addition, measuring rheological properties before and after glass former addition, and visual observation of the resulting glass coupons. Critical aspects of this unit operation are mixing and sampling of the waste and melter feeds to ensure representative samples are obtained as well as ensuring the fabrication process for the glass coupon is adequate. Testing was performed using a range of simulants (LAW and HLW simulants), and these simulants were mixed with high and low bounding amounts of GFCs to evaluate the mixing, sampling, and glass preparation steps in shielded cells using laboratory techniques. The tests were performed with off-the-shelf equipment at the Savannah River National Laboratory (SRNL) that is similar to equipment used in the SRNL work during qualification of waste feed for the Defense Waste Processing Facility (DWPF) and other waste treatment facilities at the

Integrated Advanced Microwave Sounding Unit-A (AMSU-A). Engineering Test Report: AMSU-A1 EOS Instrument, (S/N 202) Qualification Level Vibration Tests of August/September 1998, (S/O 565632, OC-417) Plus Addendum A

Science.gov (United States)

Heffer, R.

1998-01-01

The purpose of this report is to present a qualification level vibration testing performed on the S/N 202, EOS AMSU-A1 Instrument was vibration tested to qualification levels per the Ref. 1 shop order. The instrument withstood the 8 g sine sweep test, the 7.5 Grms random vibration test, and the 18.75 g sine burst test in each of the three orthogonal axes. Some loss of transmissibility, however, is seen in the lower reflector after Z-axis random vibration. The test sequence was not without incidence. Failure of Channel 7 in the Limited Performance Test (LPT) performed after completion of the 1 st (X-axis) axis vibration sequence, required replacement of the DRO and subsequent re-testing of the instrument. The post-vibration comprehensive performance test (CPT) was successfully run after completion of the three axes of vibration with the replacement component installed in the instrument. Passing the CPT signified the successful completion of the S/N 202 A1 qualification vibration testing.

Performances Study of a Hybrid Rocket Engine

Directory of Open Access Journals (Sweden)

Adrian-Nicolae BUTURACHE

2018-06-01

Full Text Available This paper presents a study which analyses the functioning and performances optimization of a hybrid rocket engine based on gaseous oxygen and polybutadiene polymer (HTPB. Calculations were performed with NASA CEA software in order to obtain the parameters resulted following the combustion process. Using these parameters, the main parameters of the hybrid rocket engine were optimized. Using the calculus previously stated, an experimental rocket engine producing 100 N of thrust was pre-dimensioned, followed by an optimization of the rocket engine as a function of several parameters. Having the geometry and the main parameters of the hybrid rocket engine combustion process, numerical simulations were performed in the CFX – ANSYS commercial software, which allowed visualizing the flow field and the jet expansion. Finally, the analytical calculus was validated through numerical simulations.

A high performance thermoacoustic Stirling-engine

Energy Technology Data Exchange (ETDEWEB)

Tijani, M.E.H.; Spoelstra, S. [Energy research Centre of the Netherlands (ECN), PO Box 1, 1755 ZG Petten (Netherlands)

2011-11-10

In thermoacoustic systems heat is converted into acoustic energy and vice versa. These systems use inert gases as working medium and have no moving parts which makes the thermoacoustic technology a serious alternative to produce mechanical or electrical power, cooling power, and heating in a sustainable and environmentally friendly way. A thermoacoustic Stirling heat engine is designed and built which achieves a record performance of 49% of the Carnot efficiency. The design and performance of the engine is presented. The engine has no moving parts and is made up of few simple components.

NFC based Equipment Qualification Management (NEQM) system preventing counterfeit and fraudulent item

Energy Technology Data Exchange (ETDEWEB)

Chang, C.K., E-mail: ckchang@kings.ac.kr [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of); Lee, K.J., E-mail: klee@khu.ac.kr [Kyung Hee Univ., Seoul (Korea, Republic of)

2014-07-01

Qualification of equipment essential to safety in nuclear power plants (NPPs) ensures its capability to perform designated safety functions on demand under postulated service conditions. However, a number of incidents identified by the NRC since 1980s catalysed the US nuclear industry to adopt standard precautions to guard against counterfeit items. The purpose of this paper is to suggest the NFC (Near Field Communication) based equipment qualification management system preventing counterfeit and fraudulent items. The NEQM (NFC based Equipment Qualification Management) system work with the support of legacy systems such as PMS (Procurement Management System) and FMS (Facility management System). (author)

NFC based Equipment Qualification Management (NEQM) system preventing counterfeit and fraudulent item

International Nuclear Information System (INIS)

Chang, C.K.; Lee, K.J.

2014-01-01

Qualification of equipment essential to safety in nuclear power plants (NPPs) ensures its capability to perform designated safety functions on demand under postulated service conditions. However, a number of incidents identified by the NRC since 1980s catalysed the US nuclear industry to adopt standard precautions to guard against counterfeit items. The purpose of this paper is to suggest the NFC (Near Field Communication) based equipment qualification management system preventing counterfeit and fraudulent items. The NEQM (NFC based Equipment Qualification Management) system work with the support of legacy systems such as PMS (Procurement Management System) and FMS (Facility management System). (author)

Concurrently adjusting interrelated control parameters to achieve optimal engine performance

Science.gov (United States)

Jiang, Li; Lee, Donghoon; Yilmaz, Hakan; Stefanopoulou, Anna

2015-12-01

Methods and systems for real-time engine control optimization are provided. A value of an engine performance variable is determined, a value of a first operating condition and a value of a second operating condition of a vehicle engine are detected, and initial values for a first engine control parameter and a second engine control parameter are determined based on the detected first operating condition and the detected second operating condition. The initial values for the first engine control parameter and the second engine control parameter are adjusted based on the determined value of the engine performance variable to cause the engine performance variable to approach a target engine performance variable. In order to cause the engine performance variable to approach the target engine performance variable, adjusting the initial value for the first engine control parameter necessitates a corresponding adjustment of the initial value for the second engine control parameter.

Instructor qualification for radiation safety training at a national laboratory

International Nuclear Information System (INIS)

Trinoskey, P.A.

1994-10-01

Prior to 1993, Health Physics Training (HPT) was conducted by the Lawrence Livermore National Laboratory (LLNL) health physics group. The job requirements specified a Masters Degree and experience. In fact, the majority of Health Physicists in the group were certified by the American Board of Health Physics. Under those circumstances, it was assumed that individuals in the group were technically qualified and the HPT instructor qualification stated that. In late 1993, the Health Physics Group at the LLNL was restructured and the training function was assigned to the training group. Additional requirements for training were mandated by the Department of Energy (DOE), which would necessitate increasing the existing training staff. With the need to hire, and the policy of reassignment of employees during downsizing, it was imperative that formal qualification standards be developed for technical knowledge. Qualification standards were in place for instructional capability. In drafting the new training qualifications for instructors, the requirements of a Certified Health Physicists had to be modified due to supply and demand. Additionally, for many of the performance-based training courses, registration by the National Registry of Radiation Protection Technologists is more desirable. Flexibility in qualification requirements has been incorporated to meet the reality of ongoing training and the compensation for desirable skills of individuals who may not meet all the criteria. The qualification requirements for an instructor rely on entry-level requirements and emphasis on goals (preferred) and continuing development of technical and instructional capabilities

Cassini radar: Instrument description and performance status

Science.gov (United States)

Johnson, W. T. K.; Im, E.; Borgarelli, L.; ZampoliniFaustini, E.

1995-01-01

The spacecraft of the Cassini mission is planned to be launched towards Saturn in October 1997. The mission is designed to study the physical structure and chemical composition of Titan. The results of the tests performed on the Cassini radar engineering qualification model (EQM) are summarized. The approach followed in the verification and evaluation of the performance of the radio frequency subsystem EQM is presented. The results show that the instrument satisfies the most relevant mission requirements.

AGR-2 Data Qualification Interim Report

International Nuclear Information System (INIS)

Abbott, Michael L.

2010-01-01

Projects for the very high temperature reactor (VHTR) Technology Development Office program provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR program established the NGNP Data Management and Analysis System (NDMAS) to manage and document VHTR data qualification, for storage of the data in a readily accessible electronic form, and to assist in the analysis and presentation of the data. This document gives the status of NDMAS processing and qualification of data associated with the initial reactor cycle (147A) of the second Advanced Gas Reactor (AGR-2) experiment which began on June 21, 2010. Because it is early in the AGR-2 experiment, data from only two AGR-2 data streams are reported on: Fuel Fabrication and Fuel Irradiation data. As of August 1, 2010, approximately 311,000 irradiation data records have been stored in NDMAS, and qualification tests are in progress. Preliminary information indicates that TC 2 in Capsule 2 failed prior to start of the experiment, and NDMAS testing has thus far identified only two invalid data values from the METSO data collection system Data from the Fission Product Monitoring System (FPMS) are not currently processed until after reactor cycle shutdown and have not yet been received. A description of the ATR operating conditions data associated with the AGR-2 experiment (e.g., power levels) are summarized in the AGR-1 data qualification report (INL/EXT-09-16460). Since ATR data are collected under ATR program data quality requirements (i.e., outside the VHTR program), the NGNP program and NDMAS do not take additional actions to qualify these data other than NDMAS capture testing. Data qualification of graphite characterization data collected under the Graphite Technology Development Project is reported in a separate status report (Hull 2010).

AGR-2 Data Qualification Interim Report

Energy Technology Data Exchange (ETDEWEB)

Michael L. Abbott

2010-09-01

Projects for the very high temperature reactor (VHTR) Technology Development Office program provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR program established the NGNP Data Management and Analysis System (NDMAS) to manage and document VHTR data qualification, for storage of the data in a readily accessible electronic form, and to assist in the analysis and presentation of the data. This document gives the status of NDMAS processing and qualification of data associated with the initial reactor cycle (147A) of the second Advanced Gas Reactor (AGR-2) experiment which began on June 21, 2010. Because it is early in the AGR-2 experiment, data from only two AGR-2 data streams are reported on: Fuel Fabrication and Fuel Irradiation data. As of August 1, 2010, approximately 311,000 irradiation data records have been stored in NDMAS, and qualification tests are in progress. Preliminary information indicates that TC 2 in Capsule 2 failed prior to start of the experiment, and NDMAS testing has thus far identified only two invalid data values from the METSO data collection system Data from the Fission Product Monitoring System (FPMS) are not currently processed until after reactor cycle shutdown and have not yet been received. A description of the ATR operating conditions data associated with the AGR-2 experiment (e.g., power levels) are summarized in the AGR-1 data qualification report (INL/EXT-09-16460). Since ATR data are collected under ATR program data quality requirements (i.e., outside the VHTR program), the NGNP program and NDMAS do not take additional actions to qualify these data other than NDMAS capture testing. Data qualification of graphite characterization data collected under the Graphite Technology Development Project is reported in a separate status report (Hull 2010).

Seismic qualification method of equipment for nuclear power plant

International Nuclear Information System (INIS)

Kim, J.S.; Choi, T.H.; Sulaimana, R.A.

1995-01-01

Safety related equipment installed in Korean Nuclear Power Plants are required to perform a safety function during and after a seismic event. To accomplish this safety function, they must be seismically qualified in accordance with the intent and requirements of the USNRC Reg. Guide 1.100 Rev. 02 and IEEE Std. 344-1987. This paper defines and summarizes acceptable criteria and procedures, based on the Korean experience, for seismic qualification of purchased equipment to be installed in a nuclear power plant. As such the paper is intended to be a concise reference by equipment designers, architectural engineering company and plant owners in uniform implementation of commitments to nuclear regulatory agencies such as the USNRC or Korea Institute of Nuclear Safety (KINS) relating to adequacy of seismic Category 1 equipment. Thus, the paper provides the methodologies which can be used for qualifying equipment for safely related service in Nuclear Power Plants in a cost effective manner

The effect of plant aging on equipment qualification and human performance issues related to license renewal

International Nuclear Information System (INIS)

Gunther, W.E.; Higgins, J.C.; Aggarwal, S.K.

1991-01-01

The aging of nuclear power plants is one of the most important issues facing the nuclear industry worldwide. Aging encompasses as forms of degradation to nuclear power plant components, systems, and structures that result from exposure to environmental conditions or from operational stresses. Both the degradation from aging and actions taken to address the aging, such as increased maintenance and testing, can significantly impact human performance in the plant. Research into the causes and effects of aging as obtained through the assessment of operating experience and testing have raised questions regarding the adequacy of existing industry standards for addressing the concerns raised by this research. This paper discusses these issues, with particular emphasis in the area of equipment qualification and human performance

The effect of plant aging on equipment qualification and human performance issues related to license renewal

Energy Technology Data Exchange (ETDEWEB)

Gunther, W.E.; Higgins, J.C. [Brookhaven National Lab., Upton, NY (United States); Aggarwal, S.K. [Nuclear Regulatory Commission, Washington, DC (United States)

1991-12-31

The aging of nuclear power plants is one of the most important issues facing the nuclear industry worldwide. Aging encompasses as forms of degradation to nuclear power plant components, systems, and structures that result from exposure to environmental conditions or from operational stresses. Both the degradation from aging and actions taken to address the aging, such as increased maintenance and testing, can significantly impact human performance in the plant. Research into the causes and effects of aging as obtained through the assessment of operating experience and testing have raised questions regarding the adequacy of existing industry standards for addressing the concerns raised by this research. This paper discusses these issues, with particular emphasis in the area of equipment qualification and human performance.

The effect of plant aging on equipment qualification and human performance issues related to license renewal

Energy Technology Data Exchange (ETDEWEB)

Gunther, W.E.; Higgins, J.C. (Brookhaven National Lab., Upton, NY (United States)); Aggarwal, S.K. (Nuclear Regulatory Commission, Washington, DC (United States))

1991-01-01

The aging of nuclear power plants is one of the most important issues facing the nuclear industry worldwide. Aging encompasses as forms of degradation to nuclear power plant components, systems, and structures that result from exposure to environmental conditions or from operational stresses. Both the degradation from aging and actions taken to address the aging, such as increased maintenance and testing, can significantly impact human performance in the plant. Research into the causes and effects of aging as obtained through the assessment of operating experience and testing have raised questions regarding the adequacy of existing industry standards for addressing the concerns raised by this research. This paper discusses these issues, with particular emphasis in the area of equipment qualification and human performance.

MTR fuel plate qualification in OSIRIS reactor

International Nuclear Information System (INIS)

Sacristan, P.; Boulcourt, P.; Naury, S.; Marchard, L.; Carcreff, H.; Noirot, J.

2005-01-01

Qualification of new MTR fuel needs the irradiation in research reactors under representative neutronic, heat flux and thermohydraulic conditions. The experiments are performed in France in the OSIRIS reactor by irradiating MTR full size fuel plates in the IRIS device located in the reactor core. The fuel plates are easily removed from the device during the shutdown of the reactor for performing thickness measurements along the plates by means of a swelling measurement device. Beside the calculation capabilities, the experimental platform includes: the ISIS neutron mock-up for the measurement of neutron flux distribution along the plates; the γ spectrometry for the purpose of measuring the activities of the radionuclides representative of the power and the burnup and to compare with the neutronic calculation. Owing to the experience feedback, a good agreement is observed between calculation and measurement; destructive post irradiation examinations in the LECA facility (Cadarache). New irradiations with the IRIS device and at higher heat flux are under preparation for qualification of MTR fuels. (author)

Integrating Multidisciplinary Engineering Knowledge

Science.gov (United States)

Wolff, Karin; Luckett, Kathy

2013-01-01

In order to design two distinct engineering qualification levels for an existing University of Technology programme, empirical evidence based on the current diploma is necessary to illuminate the nature of and the relationship between the "contextual" and "conceptual" elements underpinning a multidisciplinary engineering…

Performance of engineered barriers

International Nuclear Information System (INIS)

Rajaram, V.; Dean, P.V.; McLellan, S.A.

1997-01-01

Engineered barriers, both vertical and horizontal, have been used to isolate hazardous wastes from contact, precipitation, surface water and groundwater. The primary objective of this study was to determine the performance of subsurface barriers installed throughout the U.S. over the past 20 years to contain hazardous wastes. Evaluation of Resource Conservation and Recovery Act (RCRA) Subtitle C or equivalent caps was a secondary objective. A nationwide search was launched to select hazardous waste sites at which vertical barrier walls and/or caps had been used as the containment method. None of the sites selected had an engineered floor. From an initial list of 130 sites, 34 sites were selected on the basis of availability of monitoring data for detailed analysis of actual field performance. This paper will briefly discuss preliminary findings regarding the design, construction quality assurance/construction quality control (CQA/CQC), and monitoring at the 34 sites. In addition, the short-term performance of these sites (less than 5 years) is presented since very little long-term performance data was available

Qualification of engine-mounted components due to operational vibration

International Nuclear Information System (INIS)

Lee, B.J.; Bayat, A.

1994-01-01

The Emergency Diesel Generator (EDG) in a Nuclear Power Plant is considered to be an essential component of the plant for its safe operation. Failures of auxiliary components directly mounted on the EDG creates costly repairs, and compromises the engine's availability and reliability. Although IEEE-323 and Section III of the ASME code require addressing of safety-related components due to mechanically induced vibration, very few guidelines exist in the nuclear industry to show how this may be accounted for. Most engine vendors rely on the empirical experience data as the basis of their evaluation for vibration. Upgrade of engine controls, addition of monitoring components and other engine modifications require design and installation of new mechanical and electrical components to be mounted directly on the engine. This necessitates the evaluation of such components for engine-induced vibration which is considered to be one of the most severe design parameters. This paper presents a methodology to evaluate three categories of components; structural, mechanical, and electrical under engine vibration. The discussion for the characteristics and manipulation of engine vibration profile to be used for each component evaluation is also given. In addition, the suitability of analytical verses testing approaches is discussed for each category. An example application of the methodology is presented for a typical EDG which is currently undergoing major controls upgrade and monitoring modification

Experimental study of dual fuel engine performance using variable LPG composition and engine parameters

International Nuclear Information System (INIS)

Elnajjar, Emad; Selim, Mohamed Y.E.; Hamdan, Mohammad O.

2013-01-01

Highlights: • The effect of using variable LPG is studied. • Five fuels with propane to butane % volume ratio are: 100-70-55-25-0. • 100% Propane composition shows the highest noise levels with similar performance. • At 45° BTDC injection timing 55% Propane LPG the only fuel experience knocking. • LPG fuels gave similar engine performance, with differences in levels of noise. - Abstract: The present work investigates experimentally the effect of LPG fuel with different composition and engine parameters on the performance of a dual compression engine. Five different blends of LPG fuels are used with Propane to Butane volume ratio of 100:0, 70:30, 55:45, 25:75, and 0:100. A single cylinder, naturally aspirated, four strokes, indirectly injected, water cooled modified Ricardo E6 engine, is used in this study. The study is carried out by measuring the cylinder pressure, engine load, engine speed, crank angle, and the fuel’s flow rate. The engine performance under variable LPG fuel composition, engine load, pilot fuel injection timing, compression ratio, pilot fuel mass and engine speed, are estimated by comparing the following engine parameters: the cylinder maximum pressure, the indicated mean effective pressure, the maximum rate of pressure rise, and the thermal efficiency. The experimental data indicates that the engine parameters are playing a major role on the engine’s performance. Different LPG fuel composition did not show a major effect on the engine efficiency but directly impacted the levels of generated combustion noise

The new lattice code Paragon and its qualification for PWR core applications

International Nuclear Information System (INIS)

Ouisloumen, M.; Huria, H.C.; Mayhue, L.T.; Smith, R.M.; Kichty, M.J.; Matsumoto, H.; Tahara, Y.

2003-01-01

Paragon is a new two-dimensional transport code based on collision probability with interface current method and written entirely in Fortran 90/95. The qualification of Paragon has been completed and the results are very good. This qualification included a number of critical experiments. Comparisons to the Monte Carlo code MCNP for a wide variety of PWR assembly lattice types were also performed. In addition, Paragon-based core simulator models have been compared against PWR plant startup and operational data for a large number of plants. Some results of these calculations and also comparisons against models developed with a licensed Westinghouse lattice code, Phoenix-P, are presented. The qualification described in this paper provided the basis for the qualification of Paragon both as a validated transport code and as the nuclear data source for core simulator codes

Benefits of Digital Equipment Generic Qualification Activities

International Nuclear Information System (INIS)

Thomas, James E.; Steiman, Samuel C.

2002-01-01

As a result of nuclear power plant instrumentation and control obsolescence issues, there have been numerous activities during recent years relating to the qualification of digital equipment. Some of these activities have been 'generic' in nature in that the qualification was not limited to plant specific applications, but was intended to cover a broad base of potential applications of the digital equipment. These generic qualifications have been funded by equipment manufacturers and by utility groups and organizations. The generic activities sponsored by the Electric Power Research Institute (EPRI) have been pilot projects for an overall generic qualification approach. The primary benefit resulting from the generic qualification work to date is that a number of digital platforms and digital devices are now available for use in various nuclear safety-related applications. Many of the tests and evaluations necessary to support plant specific applications have been completed. The amount of data and documentation that each utility must develop on a case by case basis has been significantly reduced. There are also a number of additional benefits resulting from these industry efforts. The challenges and difficulties in qualifying digital equipment for safety-related applications are now more clearly understood. EPRI has published a lessons learned document (EPRI Report 1001452, Generic Qualification of Commercial Grade Digital Devices: Lessons Learned from Initial Pilots, which covers several different qualification areas, including device selection, project planning, vendor surveys and design reviews, and electromagnetic compatibility (EMC) qualification. Application of the experience and lessons learned from the EPRI pilot activities should help reduce the effort and cost required for future qualification work. Most generic qualification activities for commercial equipment have been conducted using the approach of EPRI TR-106439, Guideline on Evaluation and Acceptance

Actively cooled plasma facing components qualification, commissioning and health monitoring

International Nuclear Information System (INIS)

Escourbiac, F.; Durocher, A.; Grosman, A.; Courtois, X.; Farjon, J.-L.; Schlosser, J.; Merola, M.; Tivey, R.

2006-01-01

In modern steady state magnetic fusion devices, actively cooled plasma facing components (PFC) have to handle heat fluxes in the range of 10-20 MW/m 2 . This generates a number of engineering constraints: the armour materials must be refractory and compatible with plasma wall interaction requirements (low sputtering and/or low atomic number); the heat sink must offer high thermal conductivity, high mechanical resistance and sufficient ductility; the component cooling system -which is generally based on the circulation of pressurized water in the PFC's heat sink - must offer high thermal heat transfer efficiency. Furthermore, the assembling of the refractory armour material onto the metallic heat sink causes generic difficulties strongly depending on thermo-mechanical properties of materials and design requirements. Life time of the PFC during plasma operation are linked to their manufacturing quality, in particular they are reduced by the possible presence of flaw assembling. The fabrication of PFC in an industrial frame including their qualification and their commissioning - which consists in checking the manufacturing quality during and at the end of manufacture - is a real challenge. From experience gained at Tore Supra on carbon fibre composite flat tiles technology components, it was assessed that a set of qualifications activities must be operated during R(and)D and manufacturing phases. Dedicated Non Destructive Technique (NDT) based on advanced active infrared thermography was developed for this purpose, afterwards, correlations between NDT, high heat flux testing and thermomechanical modelling were performed to analyse damage detection and propagation, and define an acceptance criteria valuable for industrial application. Health monitoring using lock-in technique was also recently operated in-situ of the Tore Supra tokamak for detection of possible defect propagation during operations, presence of acoustic precursor for critical heat flux detection induced

Enabling performance skills: Assessment in engineering education

Science.gov (United States)

Ferrone, Jenny Kristina

Current reform in engineering education is part of a national trend emphasizing student learning as well as accountability in instruction. Assessing student performance to demonstrate accountability has become a necessity in academia. In newly adopted criterion proposed by the Accreditation Board for Engineering and Technology (ABET), undergraduates are expected to demonstrate proficiency in outcomes considered essential for graduating engineers. The case study was designed as a formative evaluation of freshman engineering students to assess the perceived effectiveness of performance skills in a design laboratory environment. The mixed methodology used both quantitative and qualitative approaches to assess students' performance skills and congruency among the respondents, based on individual, team, and faculty perceptions of team effectiveness in three ABET areas: Communications Skills. Design Skills, and Teamwork. The findings of the research were used to address future use of the assessment tool and process. The results of the study found statistically significant differences in perceptions of Teamwork Skills (p performance skills, such as teamwork, among freshman engineering students; (2) incorporate feedback into the learning process; (3) strengthen the assessment process with a follow-up plan that specifically targets performance skill deficiencies, and (4) integrate the assessment instrument and practice with ongoing curriculum development. The findings generated by this study provides engineering departments engaged in assessment activity, opportunity to reflect, refine, and develop their programs as it continues. It also extends research on ABET competencies of engineering students in an under-investigated topic of factors correlated with team processes, behavior, and student learning.

49 CFR 180.507 - Qualification of tank cars.

Science.gov (United States)

2010-10-01

... 49 Transportation 2 2010-10-01 2010-10-01 false Qualification of tank cars. 180.507 Section 180... QUALIFICATION AND MAINTENANCE OF PACKAGINGS Qualification and Maintenance of Tank Cars § 180.507 Qualification of tank cars. (a) Each tank car marked as meeting a “DOT” specification or any other tank car used...

Technological and engineering challenges of fusion

International Nuclear Information System (INIS)

Maisonnier, David; Hayward, Jim

2008-01-01

The current fusion development scenario in Europe assumes the sequential achievement of key milestones. Firstly, the qualification of the DEMO/reactor physics basis in ITER, secondly, the qualification of materials for in-vessel components in IFMIF and, thirdly, the qualification of components and processes in DEMO. Although this scenario is constrained by budgetary considerations, it assumes the resolution of many challenges in physics, technology and engineering. In the first part of the paper, the technological and engineering challenges to be met in order to satisfy the current development scenario will be highlighted. These challenges will be met by an appropriate share of the work between ITER, IFMIF, DEMO and the necessary accompanying programme, which will have to include a number of dedicated facilities (e.g. for the development of H and CD systems). In the second part of the paper, the consequences of a considerable acceleration of the fusion development programme will be discussed. Although most of the technological and engineering challenges identified above will have to be met within a shorter timescale, it is possible to limit the requirements and expectation for a first fusion power plant with respect to those adopted for the current fusion development scenario. However, it must be recognised that such a strategy will inevitably result in increased risk and a reduction in the economy of the plant. (author)

Hydrogen engine performance analysis project. Second annual report

Energy Technology Data Exchange (ETDEWEB)

Adt, Jr., R. R.; Swain, M. R.; Pappas, J. M.

1980-01-01

Progress in a 3 year research program to evaluate the performance and emission characteristics of hydrogen-fueled internal combustion engines is reported. Fifteen hydrogen engine configurations will be subjected to performance and emissions characterization tests. During the first two years, baseline data for throttled and unthrottled, carburetted and timed hydrogen induction, Pre IVC hydrogen-fueled engine configurations, with and without exhaust gas recirculation (EGR) and water injection, were obtained. These data, along with descriptions of the test engine and its components, the test apparatus, experimental techniques, experiments performed and the results obtained, are given. Analyses of other hydrogen-engine project data are also presented and compared with the results of the present effort. The unthrottled engine vis-a-vis the throttled engine is found, in general, to exhibit higher brake thermal efficiency. The unthrottled engine also yields lower NO/sub x/ emissions, which were found to be a strong function of fuel-air equivalence ratio. (LCL)

The Qualification Experiences for Safety-critical Software of POSAFE-Q

Energy Technology Data Exchange (ETDEWEB)

Kim, Jang Yeol; Son, Kwang Seop; Cheon, Se Woo; Lee, Jang Soo; Kwon, Kee Choon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2009-05-15

Programmable Logic Controllers (PLC) have been applied to the Reactor Protection System (RPS) and the Engineered Safety Feature (ESF)-Component Control System (CCS) as the major safety system components of nuclear power plants. This paper describes experiences on the qualification of the safety-critical software including the pCOS kernel and system tasks related to a safety-grade PLC, i.e. the works done for the Software Verification and Validation, Software Safety Analysis, Software Quality Assurance, and Software Configuration Management etc.

Performance comparison of a novel configuration of beta-type Stirling engines with rhombic drive engine

International Nuclear Information System (INIS)

Solmaz, Hamit; Karabulut, Halit

2014-01-01

Highlights: • The paper describes a novel arrangement of a beta-type Stirling engine. • Its performance was compared with rhombic drive engine. • The power output of the engine was found to be greater than rhombic drive. • Efficiency was found to be higher than rhombic drive at the same working fluid mass. • Efficiency was found to be lower than rhombic drive at the same charge pressure. - Abstract: This study presents a beta type Stirling engine mechanism and its performance analysis. The displacer motion of the engine is performed by a lever mechanism. The performance of the engine was investigated via comparing with a rhombic-drive engine possessing an equal sided rhombic. Comparison was made for kinematic behaviors, power and thermal efficiency. For comparison; the piston swept volume, the inner heat transfer area, the hot and cold end temperatures, the inner heat transfer coefficient, charge pressure and dead volumes were kept equal for both engines. As working fluid the helium was used. Thermodynamic treatments of engines were performed via the nodal analysis. The power of the lever driven engine was found to be greater than the power of the rhombic drive engine. Under the equal charge pressure, the thermal efficiency of the lever driven engine was found to be lower than the efficiency of the rhombic drive engine however, under the equal working fluid mass the thermal efficiency of the lever driven engine was found to be greater than that of the rhombic drive engine. The external volume and mass of the lever driven engine is lower than the rhombic drive engine

Nuclear security personnel for power plants. Content and review procedures for a security training and qualification program

International Nuclear Information System (INIS)

1978-06-01

The applicant and licensee training and qualification plans will outline the process by which guard, watchman, armed response persons and other members of the security organization will be selected, trained, equipped and qualified. This plan should contain: (1) job descriptions for all security positions; (2) duties defined for all positions; (3) critical tasks defined for all duties; (4) skills, knowledge and abilities defined for all critical tasks; (5) performance objectives stated for all critical tasks; and (6) training and qualification plans to train and test to appropriate performance objectives. The document gives guidance on the preparation of this training and qualification plan and contains three parts: (1) an introduction to and brief explanation of job analysis and performance objectives; (2) a statement of the information that should be submitted in response to the requirements and the NRR review procedures; and (3) a sample qualification submittal

ENIQ: European Network for Inspection Qualification

International Nuclear Information System (INIS)

Champigny, F.; Crutzen, S.; Lemaitre, P.

1995-01-01

Many countries are currently considering their own approach to inspection qualification and are carefully assessing experience to date. ENIQ, which stands for European Network for Inspection Qualification, groups the major part of the utilities in Western Europe. The general objective of ENIQ is to coordinate and manage at European level expertise and resources for the assessment and qualification of NDE inspection techniques and procedures, primarily for nuclear components. Also non-nuclear heavy duty components will be considered. Within ENIQ there is a growing consensus of opinion on the general principles of a European approach towards inspection qualification. In this paper the main activities, organization and actual status of ENIQ will be discussed

On ISI effectiveness through inspection qualification

International Nuclear Information System (INIS)

Harutyunov, R.

2000-01-01

There are two units of WWER type in the ANPP. The results of the implementation of the IAEA qualification guidelines for the ANPP Primary Circuit for WWER are presented. The control methods according to the ISI Program are foreseen in the design and implemented during the preparation for the unit 2 restart. The result of control is plugging of more tubes than during the last operation period. During the next years in the presence of the blowdown water activity, the search on defective tubes was performed by Lumhydraulic methods and the tubes were plugged by welding plugs. In 1999 was performed the visual control on the Steam Generator 6 by WNIAES experts and by the ANPP experts from the Metal Laboratory. The result is confirmation of the irreversible process on erosive-corrosion destruction of feed waters distribution header; definition of the defects coordinates defined; detection of sediments within the SG vessel surfaces and in the head exchanged surface tubes. The purpose of the ISI effectiveness improvement is to discover the defects in the base metal and in the welds before developing into a problem at operating level or a safety problem. For the solution on the specific problems at the ANPP the project for technological co-operation with IAEA has been developed. It is necessary to organize training, certification, assessment methodology. The expected results after the project implementation are to establish the base for the equipment qualification body and staff certification; to upgrade the ANPP staff qualification; to prepare a group of experts, supported by ANRA, which to be also involved in the development of NDM national regulators

40 CFR 35.937 - Subagreements for architectural or engineering services.

Science.gov (United States)

2010-07-01

... competence and qualifications for the type of professional services required and at fair and reasonable... announcement of the requirements for personal and professional services, including engineering services... engineering services. Those professional services associated with research, development, design and...

Self-Control and Academic Performance in Engineering

Science.gov (United States)

Honken, Nora; Ralston, Patricia A.; Tretter, Thomas R.

2016-01-01

Self-control has been related to positive student outcomes including academic performance of college students. Because of the critical nature of the first semester academic performance for engineering students in terms of retention and persistence in pursuing an engineering degree, this study investigated the relationship between freshmen…

Engineering Self-Efficacy Contributing to the Academic Performance of AMAIUB Engineering Students: A Qualitative Investigation

Science.gov (United States)

Aleta, Beda T.

2016-01-01

This research study aims to determine the factors of engineering skills self- efficacy sources contributing on the academic performance of AMAIUB engineering students. Thus, a better measure of engineering self-efficacy is needed to adequately assess engineering students' beliefs in their capabilities to perform tasks in their engineering…

Materials qualification for nuclear power plants

International Nuclear Information System (INIS)

Braconi, F.

1987-01-01

The supply of materials to be used in the fabrication of components submitted to pressure destined to Atucha II nuclear power plant must fulfill the quality assurance requirements in accordance with the international standards. With the aim of promoting the national participation in CNA II, ENACE had the need to adapt these requirements to the national industry conditions and to the availability of official entities' qualification and inspection. As a uniform and normalized assessment for the qualification of materials did not exist in the country, ENACE had to develop a materials suppliers qualification system. This paper presents a suppliers qualification procedure, its application limits and the alternative procedures for the acceptance of individual stock and for the stock materials purchase. (Author)

Photovoltaic Engineering Testbed: A Facility for Space Calibration and Measurement of Solar Cells on the International Space Station

Science.gov (United States)

Landis, Geoffrey A.; Bailey, Sheila G.; Jenkins, Phillip; Sexton, J. Andrew; Scheiman, David; Christie, Robert; Charpie, James; Gerber, Scott S.; Johnson, D. Bruce

2001-01-01

The Photovoltaic Engineering Testbed ("PET") is a facility to be flown on the International Space Station to perform calibration, measurement, and qualification of solar cells in the space environment and then returning the cells to Earth for laboratory use. PET will allow rapid turnaround testing of new photovoltaic technology under AM0 conditions.

Qualification of code-Saturne for thermal-hydraulics single phase nuclear applications

International Nuclear Information System (INIS)

Archambeau, F.; Bechaud, C.; Gest, B.; Martin, A.; Sakiz, M.

2003-01-01

Code-Saturne is a general finite volume CFD (computational fluid dynamics) code developed by Electricite de France (EDF) under quality assurance for 2- and 3-dimensional simulations, laminar and turbulent flows, conjugate heat transfer (coupling with thermal code SYRTHES), including combustion modelling and a Lagrangian module. A very large range of meshes can be used. The solver relies on a finite volume method on arbitrary meshes (hybrid, with hanging nodes, any type of element). All variables are located at the cell centres. The solver is time marching, with a predictor-corrector scheme for Navier-Stokes equations. Standard Reynolds Average Navier-Stokes modelling (RANS) is included (k-epsilon, RSM). Code-Saturne is used by EDF in various industrial fields such as process engineering, aeraulics, combustion and nuclear applications. The present paper describes the qualification phase carried out during 2001 for single-phase nuclear applications. Indeed, once an industrial product has been released and validated, it is of major importance, especially in this particular field related to safety matters, to demonstrate the ability of the code to help engineers produce satisfactory conclusions to industrial problems. In coherence with analyses and best practice guidelines such as those published by the ERCOFTAC Special Interest Group, it seemed important to base the qualification phase on well defined and documented experimental facilities, sufficiently complex to be representative of industrial studies. Much attention has been devoted to evaluating sensitivity to numerical parameters such as grid refinement, time step... Moreover, the qualification studies have been carried out in real-life conditions, that is in limited time, with industrial limitations on the number of grid cells, and by the teams usually producing such studies, so as to integrate a real industrial process in the qualification phase. Two test cases chosen to assess certain types of flows in PWR

Qualification tests for a type B (U) package

International Nuclear Information System (INIS)

Vieru, G.

2004-01-01

The primary objective for the safety of radioactive materials transport is to protect human health and the environment taking into consideration its potential risks and radiological consequences. Romania as a Member State of the International Atomic Energy Agency has implemented national regulations for the safe transport of radioactive materials (RAM) in accordance with the Agency's recommendations as well as other international specialized organizations. The paper will describe the qualification tests performed for a type B (U) package, intended to be used for the transport of the radioactive sources Am-241 and Cs-137. For this kind of package the tests were performed the first time in Romania and include: the water spray test, the 1.2 m free drop test, the stacking test, the penetration test, the 9m free drop test, the thermal test and the submersion under a head of water of at least 15 m. The test facilities used for performing qualification tests for the type B (U) package as well as experience and conclusions will be also presented

Establishment of an unrelated umbilical cord blood bank qualification program: ensuring quality while meeting Food and Drug Administration vendor qualification requirements.

Science.gov (United States)

Rabe, Fran; Kadidlo, Diane; Van Orsow, Lisa; McKenna, David

2013-10-01

Qualification of a cord blood bank (CBB) is a complex process that includes evaluation of multiple aspects of donor screening and testing, processing, accreditation and approval by professional cell therapy groups, and results of received cord blood units. The University of Minnesota Medical Center Cell Therapy Laboratory has established a CBB vendor qualification process to ensure the CBB meets established regulatory and quality requirements. The deployed qualification of CBBs is based on retrospective and prospective review of the CBB. Forty-one CBBs were evaluated retrospectively: seven CBBs were disqualified based on failed quality control (QC) results. Eight CBBs did not meet the criteria for retrospective qualification because fewer than 3 cord blood units were received and the CBB was not accredited. As of March 2012, three US and one non-US CBBs have been qualified prospectively. One CBB withdrew from the qualification process after successful completion of the comprehensive survey and subsequent failure of the provided QC unit to pass the minimum criteria. One CBB failed the prospective qualification process based on processing methods that were revealed during the paper portion of the evaluation. A CBB qualification process is necessary for a transplant center to manage the qualification of the large number of CBBs needed to support a umbilical cord blood transplantation program. A transplant center that has utilized cord blood for a number of years before implementation of a qualification process should use a retrospective qualification process along with a prospective process. © 2013 American Association of Blood Banks.

Enhanced Engine Performance During Emergency Operation Using a Model-Based Engine Control Architecture

Science.gov (United States)

Csank, Jeffrey T.; Connolly, Joseph W.

2016-01-01

This paper discusses the design and application of model-based engine control (MBEC) for use during emergency operation of the aircraft. The MBEC methodology is applied to the Commercial Modular Aero-Propulsion System Simulation 40k (CMAPSS40k) and features an optimal tuner Kalman Filter (OTKF) to estimate unmeasured engine parameters, which can then be used for control. During an emergency scenario, normally-conservative engine operating limits may be relaxed to increase the performance of the engine and overall survivability of the aircraft; this comes at the cost of additional risk of an engine failure. The MBEC architecture offers the advantage of estimating key engine parameters that are not directly measureable. Estimating the unknown parameters allows for tighter control over these parameters, and on the level of risk the engine will operate at. This will allow the engine to achieve better performance than possible when operating to more conservative limits on a related, measurable parameter.

The Bologna Process, Globalisation and Engineering Education Developments

Science.gov (United States)

Uhomoibhi, James O.

2009-01-01

Purpose: The purpose of this paper is to report on the Bologna Process in the light of globalisation and examine how it affects curriculum and engineering education developments. Design/methodology/approach: The growing need for creative competitiveness and the striving for specific profiles of engineering qualifications that are of high quality…

Training and qualification program for nuclear criticality safety technical staff. Revision 1

International Nuclear Information System (INIS)

Taylor, R.G.; Worley, C.A.

1997-01-01

A training and qualification program for nuclear criticality safety technical staff personnel has been developed and implemented. All personnel who are to perform nuclear criticality safety technical work are required to participate in the program. The program includes both general nuclear criticality safety and plant specific knowledge components. Advantage can be taken of previous experience for that knowledge which is portable such as performance of computer calculations. Candidates step through a structured process which exposes them to basic background information, general plant information, and plant specific information which they need to safely and competently perform their jobs. Extensive documentation is generated to demonstrate that candidates have met the standards established for qualification

Performance and driveline analyses of engine capacity in range extender engine hybrid vehicle

Science.gov (United States)

Praptijanto, Achmad; Santoso, Widodo Budi; Nur, Arifin; Wahono, Bambang; Putrasari, Yanuandri

2017-01-01

In this study, range extender engine designed should be able to meet the power needs of a power generator of hybrid electrical vehicle that has a minimum of 18 kW. Using this baseline model, the following range extenders will be compared between conventional SI piston engine (Baseline, BsL), engine capacity 1998 cm3, and efficiency-oriented SI piston with engine capacity 999 cm3 and 499 cm3 with 86 mm bore and stroke square gasoline engine in the performance, emission prediction of range extender engine, standard of charge by using engine and vehicle simulation software tools. In AVL Boost simulation software, range extender engine simulated from 1000 to 6000 rpm engine loads. The highest peak engine power brake reached up to 38 kW at 4500 rpm. On the other hand the highest torque achieved in 100 Nm at 3500 rpm. After that using AVL cruise simulation software, the model of range extended electric vehicle in series configuration with main components such as internal combustion engine, generator, electric motor, battery and the arthemis model rural road cycle was used to simulate the vehicle model. The simulation results show that engine with engine capacity 999 cm3 reported the economical performances of the engine and the emission and the control of engine cycle parameters.

Cassini Radar EQM Model: Instrument Description and Performance Status

Science.gov (United States)

Borgarelli, L.; Faustini, E. Zampolini; Im, E.; Johnson, W. T. K.

1996-01-01

The spaeccraft of the Cassini Mission is planned to be launched towards Saturn in October 1997. The mission is designed to study the physical structure and chemical composition of Titan. The results of the tests performed on the Cassini radar engineering qualification model (EQM) are summarized. The approach followed in the verification and evaluation of the performance of the radio frequency subsystem EQM is presented. The results show that the instrument satisfies the relevant mission requirements.

Standard guide for the selection, training and qualification of nondestructive assay (NDA) personnel

CERN Document Server

American Society for Testing and Materials. Philadelphia

2004-01-01

1.1 This guide contains good practices for the selection, training, qualification, and professional development of personnel performing analysis, calibration, physical measurements, or data review using nondestructive assay equipment, methods, results, or techniques. The guide also covers NDA personnel involved with NDA equipment setup, selection, diagnosis, troubleshooting, or repair. Selection, training, and qualification programs based on this guide are intended to provide assurance that NDA personnel are qualified to perform their jobs competently. This guide presents a series of options but does not recommend a specific course of action.

Sludge Batch 7B Qualification Activities With SRS Tank Farm Sludge

International Nuclear Information System (INIS)

Pareizs, J.; Click, D.; Lambert, D.; Reboul, S.

2011-01-01

Waste Solidification Engineering (WSE) has requested that characterization and a radioactive demonstration of the next batch of sludge slurry - Sludge Batch 7b (SB7b) - be completed in the Shielded Cells Facility of the Savannah River National Laboratory (SRNL) via a Technical Task Request (TTR). This characterization and demonstration, or sludge batch qualification process, is required prior to transfer of the sludge from Tank 51 to the Defense Waste Processing Facility (DWPF) feed tank (Tank 40). The current WSE practice is to prepare sludge batches in Tank 51 by transferring sludge from other tanks. Discharges of nuclear materials from H Canyon are often added to Tank 51 during sludge batch preparation. The sludge is washed and transferred to Tank 40, the current DWPF feed tank. Prior to transfer of Tank 51 to Tank 40, SRNL typically simulates the Tank Farm and DWPF processes with a Tank 51 sample (referred to as the qualification sample). With the tight schedule constraints for SB7b and the potential need for caustic addition to allow for an acceptable glass processing window, the qualification for SB7b was approached differently than past batches. For SB7b, SRNL prepared a Tank 51 and a Tank 40 sample for qualification. SRNL did not receive the qualification sample from Tank 51 nor did it simulate all of the Tank Farm washing and decanting operations. Instead, SRNL prepared a Tank 51 SB7b sample from samples of Tank 7 and Tank 51, along with a wash solution to adjust the supernatant composition to the final SB7b Tank 51 Tank Farm projections. SRNL then prepared a sample to represent SB7b in Tank 40 by combining portions of the SRNL-prepared Tank 51 SB7b sample and a Tank 40 Sludge Batch 7a (SB7a) sample. The blended sample was 71% Tank 40 (SB7a) and 29% Tank 7/Tank 51 on an insoluble solids basis. This sample is referred to as the SB7b Qualification Sample. The blend represented the highest projected Tank 40 heel (as of May 25, 2011), and thus, the highest

Instrumentation qualification. Seismic qualification of C-E instrumentation equipment. Part One

International Nuclear Information System (INIS)

1977-05-01

A summary of the C-E seismic qualification program utilized to demonstrate the seismic design adequacy of the instrumentation and control equipment used in C-E supplied Nuclear Steam Supply Systems (NSSS) is presented. The report is divided into two parts. Part One includes the equipment seismic requirements and a description of the qualification methods. Part Two lists the specific equipment by nuclear station in which it is used and the equipment test results are summarized in a standard data sheet format to facilitate review. The seismic requirements are based on individual contract commitments with C-E customers and the NRC Standard Review Plan, Section 3.10 ''Seismic Qualification of Category I Instrumentation and Electrical Equipment.'' Equipment is qualified for use in a seismic environment where damage potential to the equipment is less than or equal to that simulated seismic environment to which it has been qualified. The anticipated Safe Shutdown Earthquake (SSE) environment at the inservice location of equipment should be confirmed by each applicant as not exceeding that to which it is qualified

Large Bore Powder Gun Qualification (U)

Energy Technology Data Exchange (ETDEWEB)

Rabern, Donald A. [Los Alamos National Laboratory; Valdiviez, Robert [Los Alamos National Laboratory

2012-04-02

A Large Bore Powder Gun (LBPG) is being designed to enable experimentalists to characterize material behavior outside the capabilities of the NNSS JASPER and LANL TA-55 PF-4 guns. The combination of these three guns will create a capability to conduct impact experiments over a wide range of pressures and shock profiles. The Large Bore Powder Gun will be fielded at the Nevada National Security Site (NNSS) U1a Complex. The Complex is nearly 1000 ft below ground with dedicated drifts for testing, instrumentation, and post-shot entombment. To ensure the reliability, safety, and performance of the LBPG, a qualification plan has been established and documented here. Requirements for the LBPG have been established and documented in WE-14-TR-0065 U A, Large Bore Powder Gun Customer Requirements. The document includes the requirements for the physics experiments, the gun and confinement systems, and operations at NNSS. A detailed description of the requirements is established in that document and is referred to and quoted throughout this document. Two Gun and Confinement Systems will be fielded. The Prototype Gun will be used primarily to characterize the gun and confinement performance and be the primary platform for qualification actions. This gun will also be used to investigate and qualify target and diagnostic modifications through the life of the program (U1a.104 Drift). An identical gun, the Physics Gun, will be fielded for confirmatory and Pu experiments (U1a.102D Drift). Both guns will be qualified for operation. The Gun and Confinement System design will be qualified through analysis, inspection, and testing using the Prototype Gun for the majority of process. The Physics Gun will be qualified through inspection and a limited number of qualification tests to ensure performance and behavior equivalent to the Prototype gun. Figure 1.1 shows the partial configuration of U1a and the locations of the Prototype and Physics Gun/Confinement Systems.

Actual waste demonstration of the nitric-glycolic flowsheet for sludge batch 9 qualification

Energy Technology Data Exchange (ETDEWEB)

Newell, D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Pareizs, J. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Martino, C. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Reboul, S. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Coleman, C. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Edwards, T. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Johnson, F. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2017-03-09

For each sludge batch that is processed in the Defense Waste Processing Facility (DWPF), the Savannah River National Laboratory (SRNL) performs qualification testing to demonstrate that the sludge batch is processable. Based on the results of this actual-waste qualification and previous simulant studies, SRNL recommends implementation of the nitric-glycolic acid flowsheet in DWPF. Other recommendations resulting from this demonstration are reported in section 5.0.

Influence of hydrox on spark ignition engine performance

International Nuclear Information System (INIS)

Naude, A.F.

2003-01-01

An experimental investigation was performed on the influence of the addition of small quantities of Hydrox (hydrogen and oxygen) as generated through electrolysis of water on the performance of a spark ignition engine. A Mazda 1600 cc fuel injected engine connected to a Superflow SF901 dynamometer system was used in this project. The engine was also equipped with a Unichip engine management system in order to enable changes in the spark timing and the amount of fuel injected. Hydrox was generated by an electrolysis process that could either be powered by the engine's alternator or from a separate power source. This hydrox gas produced from the electrolyzer was introduced into the engine's intake manifold and the influence of this was measured on the engine's performance, emissions and fuel consumption. For these tests a typical load condition as experienced for a light passenger car vehicle driven at 100 km/h on the open road was simulated. Typical results for the change in emissions with the hydrox introduction showed a significant reduction in hydrocarbons at lean air-fuel ratio operation of the engine. Additionally with the electrolysis process being driven by the engine a small improvement in fuel consumption was experienced. (author)

Technical basis for environmental qualification of computer-based safety systems in nuclear power plants

International Nuclear Information System (INIS)

Korsah, K.; Wood, R.T.; Tanaka, T.J.; Antonescu, C.E.

1997-01-01

This paper summarizes the results of research sponsored by the US Nuclear Regulatory Commission (NRC) to provide the technical basis for environmental qualification of computer-based safety equipment in nuclear power plants. This research was conducted by the Oak Ridge National Laboratory (ORNL) and Sandia National Laboratories (SNL). ORNL investigated potential failure modes and vulnerabilities of microprocessor-based technologies to environmental stressors, including electromagnetic/radio-frequency interference, temperature, humidity, and smoke exposure. An experimental digital safety channel (EDSC) was constructed for the tests. SNL performed smoke exposure tests on digital components and circuit boards to determine failure mechanisms and the effect of different packaging techniques on smoke susceptibility. These studies are expected to provide recommendations for environmental qualification of digital safety systems by addressing the following: (1) adequacy of the present preferred test methods for qualification of digital I and C systems; (2) preferred standards; (3) recommended stressors to be included in the qualification process during type testing; (4) resolution of need for accelerated aging in qualification testing for equipment that is to be located in mild environments; and (5) determination of an appropriate approach to address smoke in a qualification program

Employers’ View on Problems Related to Workforce Skills and Qualification

Directory of Open Access Journals (Sweden)

Klimplová Lenka

2012-12-01

Full Text Available The aim of this exploratory study is to reveal employers’ views on problems related to workforce human capital (skills and qualification. Where do employers themselves view the core of difficulties with ensuring adequately skilled workforce? Do they assign them to technological and organizational changes (a functional concept of job-specific human capital obsolescence, or do they see these problems as a result of other circumstances, such as macro-structural conditions or institutional settings? To answer these questions selected employers in mechanical engineering and information technology sectors in the Czech Republic were interviewed. The results show that the employers see the problems: 1 on the side of workforce – insufficient abilities and skills, exaggerated demands and low motivation; 2 as inadequate capacities and capabilities of the organization itself; 3 at macro-level as institutional shortcomings in the initial educational system and social benefits system. The problems related to workforce skills and qualification cannot be, thus, interpreted only in the functionalist view as job-specific human capital obsolescence, but the formulation of the problems is significantly affected by the institutional framework.

Nuclear energy electricity technical regulation on the qualification

International Nuclear Information System (INIS)

1995-01-01

It tells the range of application purpose and of the qualification. It describes how to qualify of the class 1 E equipment, which are type test, operating experience, analysis and combined method. Next it deals with qualification procedure, which are specification requirement, requirement of qualification program, type testing, operating experience, analysis and combined qualification, acceptance criteria modification and extension with qualified life, simulated test profiles and document about type test data, operating experience data and extrapolation.

Changing existing qualifications into outcomes-based qualifications ...

African Journals Online (AJOL)

Various workshops were facilitated to determine the outcomes of each level of our qualification, B Tech: Policing. This led to the formulation of a purpose statement, exit level outcomes and specific outcomes as well as assessment criteria and the critical outcomes embedded in each level identified. Using the specific ...

42 CFR 493.1469 - Standard: Cytology general supervisor qualifications.

Science.gov (United States)

2010-10-01

... 42 Public Health 5 2010-10-01 2010-10-01 false Standard: Cytology general supervisor... Nonwaived Testing Laboratories Performing High Complexity Testing § 493.1469 Standard: Cytology general supervisor qualifications. The cytology general supervisor must be qualified to supervise cytology services...

Report on investigation in fiscal 2000 on the overall investigation on engineers' lifetime education system; 2000 nendo gijutsusha shogai kyoiku system zentai chosa hokokusho

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-03-01

This investigative research is intended to propose means to solve problems in the continuing professional development (CPD) under the situation where the works on international applicability of the engineer qualification are varying fluidly. The research has investigated and studied the preferable forms of the CPD, its operation methods, and systems. The conclusion may be summarized as follows: as the ways the CPD and the engineer qualification should be, the CPD should preferably be implemented by each academic society along the guidelines prepared by the Japan Council for Overall Process of Continuing Capability Development (PDE).; the engineer qualification should be set by the government or a unified certifying organization corresponding to the government, who will establish the basic rules and standards to certify and provide the qualifications uniting all the academic societies; it will be necessary to provide the CPD participants with the supporting measures by which they all feel 'something to live for'; for instance, business entities must be approached so that the qualifications are reflected to personnel management, pay raise, and status promotion as a proof of enhancement in their endowments and capabilities; and with regard to the mutual cooperation between the academic society CPD and the engineer CPD, a cooperative system may be structured by having the Japan Engineering Society conclude an agreement with the Japan Engineers Society. (NEDO)

48 CFR 1553.209 - Contractor qualifications.

Science.gov (United States)

2010-10-01

... 48 Federal Acquisition Regulations System 6 2010-10-01 2010-10-01 true Contractor qualifications. 1553.209 Section 1553.209 Federal Acquisition Regulations System ENVIRONMENTAL PROTECTION AGENCY CLAUSES AND FORMS FORMS Prescription of Forms 1553.209 Contractor qualifications. ...

On relaxing the Mangasarian-Fromovitz constraint qualification

Czech Academy of Sciences Publication Activity Database

Kruger, A.Y.; Minchenko, L.; Outrata, Jiří

2014-01-01

Roč. 18, č. 1 (2014), s. 171-189 ISSN 1385-1292 R&D Projects: GA ČR GAP402/12/1309 Institutional support: RVO:67985556 Keywords : Nonlinear programming * Regularity conditions * Constraint qualifications * Lagrange multipliers * Mangasarian–Fromovitz constraint qualification * Constant rank constraint qualification Subject RIV: BA - General Mathematics Impact factor: 0.679, year: 2014 http://library.utia.cas.cz/separaty/2014/MTR/outrata-0426110.pdf

5 CFR 317.502 - Qualifications Review Board certification.

Science.gov (United States)

2010-01-01

... REGULATIONS EMPLOYMENT IN THE SENIOR EXECUTIVE SERVICE Career Appointments § 317.502 Qualifications Review Board certification. (a) A Qualification Review Board (QRB) convened by OPM must certify the executive... 5 Administrative Personnel 1 2010-01-01 2010-01-01 false Qualifications Review Board certification...

Nuclear Criticality Safety Department Qualification Program

International Nuclear Information System (INIS)

Carroll, K.J.; Taylor, R.G.; Worley, C.A.

1996-01-01

The Nuclear Criticality Safety Department (NCSD) is committed to developing and maintaining a staff of highly qualified personnel to meet the current and anticipated needs in Nuclear Criticality Safety (NCS) at the Oak Ridge Y-12 Plant. This document defines the Qualification Program to address the NCSD technical and managerial qualification as required by the Y-1 2 Training Implementation Matrix (TIM). This Qualification Program is in compliance with DOE Order 5480.20A and applicable Lockheed Martin Energy Systems, Inc. (LMES) and Y-1 2 Plant procedures. It is implemented through a combination of WES plant-wide training courses and professional nuclear criticality safety training provided within the department. This document supersedes Y/DD-694, Revision 2, 2/27/96, Qualification Program, Nuclear Criticality Safety Department There are no backfit requirements associated with revisions to this document

48 CFR 53.209 - Contractor qualifications.

Science.gov (United States)

2010-10-01

... 48 Federal Acquisition Regulations System 2 2010-10-01 2010-10-01 false Contractor qualifications. 53.209 Section 53.209 Federal Acquisition Regulations System FEDERAL ACQUISITION REGULATION (CONTINUED) CLAUSES AND FORMS FORMS Prescription of Forms 53.209 Contractor qualifications. ...

Seismic qualification of the rotary relay for use in the solid state protection system

International Nuclear Information System (INIS)

Vogeding, E.L.; Jarecki, S.J.

1976-01-01

The seismic qualification of a rotary relay that can be used as a replacement for the type of relay located in the output section of the Solid State Protection System is described. The qualification test results indicate that the tested relays did not exhibit any contact bounce or abnormal operation; they performed satisfactorily before, during, and after the simulated seismic vibration tests

Report on surveys in fiscal 2000 on the survey on foundation to establish industrial technology strategy. Survey on lifetime education for mechanical engineers; 2000 nendo sangyo gijutsu senryaku sakusei kiban chosa hokokusho. Kikai gijutsusha shogai kyoiku chosa

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-03-01

With an objective to set up a system for full-scale lifetime education, a feasibility study has been performed on preparing new educational materials and performing seminars. The continuing education program developed by the Japan Society of Mechanical Engineers is intended to assist engineers studied under the new engineer system to accumulate actual work experience after having acquired the qualification, and motivate ability maintenance and self-enlightenment after having acquired the engineer qualification, mainly through the training meetings and lecture meetings held by the Japan Society of Mechanical Engineers. The education items in the major field course include dynamics of materials and machines, energy and flow, information and control, and design and production. The items in the general common course include presentation and communication, kinetics learned from actual cases, engineer ethics, product liability and product safety. The seminar was held for two days for engineers graduated from undergraduate departments and experienced in actual works for two years or longer as the object. The actual status survey related to the continuing education by corporations revealed that 83% of the corporations has implemented intra-corporation training, and encouraged positive participation to outside seminars. (NEDO)

Methods for qualification of highly reliable software - international procedure

International Nuclear Information System (INIS)

Kersken, M.

1997-01-01

Despite the advantages of computer-assisted safety technology, there still is some uneasyness to be observed with respect to the novel processes, resulting from absence of a body of generally accepted and uncontentious qualification guides (regulatory provisions, standards) for safety evaluation of the computer codes applied. Warranty of adequate protection of the population, operators or plant components is an essential aspect in this context, too - as it is in general with reliability and risk assessment of novel technology - so that, due to appropriate legislation still missing, there currently is a licensing risk involved in the introduction of digital safety systems. Nevertheless, there is some extent of agreement within the international community and utility operators about what standards and measures should be applied for qualification of software of relevance to plant safety. The standard IEC 880/IEC 86/ in particular, in its original version, or national documents based on this standard, are applied in all countries using or planning to install those systems. A novel supplement to this standard, document /IEC 96/, is in the process of finalization and defines the requirements to be met by modern methods of software engineering. (orig./DG) [de

An analysis of the qualification criteria for small radioactive material shipping packages

International Nuclear Information System (INIS)

McClure, J.D.

1983-05-01

The RAM package design certification process has two important elements, testing and acceptance. These terms sound very similar but they have specific meanings. Qualification testing in the context of this study is the imposition of simulated accident test conditions upon the candidate package design. (Normal transportation environments may also be included.) Following qualification testing, the acceptance criteria provide the performance levels which, if demonstrated, indicate the ability of the RAM package to sustain the severity of the qualification testing sequence and yet maintain specified levels of package integrity. This study has used Severities of Transportation Accidents as a data base to examine the regulatory test criteria which are required to be met by small packages containing Type B quantities of radioactive material (RAM). The basic findings indicate that the present regulatory test standards provide significantly higher levels of protection for the surface transportation modes (truck, rail) than for RAM packages shipped by aircraft. It should also be noted that various risk assessment studies have shown that the risk to the public due to severe transport accidents by surface and air transport modes is very low. A key element in this study was the quantification of the severity of the transportation accident environment and the severity of the present qualification test standards (called qualification test standards in this document) so that a direct comparison could be made between them to assess the effectiveness of the existing qualification test standards. The manner in which this was accomplished is described

An analysis of the qualification criteria for small radioactive material shipping packages

Energy Technology Data Exchange (ETDEWEB)

McClure, J.D.

1983-05-01

The RAM package design certification process has two important elements, testing and acceptance. These terms sound very similar but they have specific meanings. Qualification testing in the context of this study is the imposition of simulated accident test conditions upon the candidate package design. (Normal transportation environments may also be included.) Following qualification testing, the acceptance criteria provide the performance levels which, if demonstrated, indicate the ability of the RAM package to sustain the severity of the qualification testing sequence and yet maintain specified levels of package integrity. This study has used Severities of Transportation Accidents as a data base to examine the regulatory test criteria which are required to be met by small packages containing Type B quantities of radioactive material (RAM). The basic findings indicate that the present regulatory test standards provide significantly higher levels of protection for the surface transportation modes (truck, rail) than for RAM packages shipped by aircraft. It should also be noted that various risk assessment studies have shown that the risk to the public due to severe transport accidents by surface and air transport modes is very low. A key element in this study was the quantification of the severity of the transportation accident environment and the severity of the present qualification test standards (called qualification test standards in this document) so that a direct comparison could be made between them to assess the effectiveness of the existing qualification test standards. The manner in which this was accomplished is described.

Qualification of a truly distributed fiber optic technique for strain and temperature measurements in concrete structures

Science.gov (United States)

Henault, J. M.; Salin, J.; Moreau, G.; Delepine-Lesoille, S.; Bertand, J.; Taillade, F.; Quiertant, M.; Benzarti, K.

2011-04-01

Structural health monitoring is a key factor in life cycle management of infrastructures. Truly distributed fiber optic sensors are able to provide relevant information on large structures, such as nuclear power plants or nuclear waste disposal facilities. The sensing chain includes an optoelectronic unit and a sensing cable made of one or more optical fibers. A new instrument based on Optical Frequency Domain Reflectometry (OFDR), enables to perform temperature and strain measurements with a centimeter scale spatial resolution over hundred of meters and with a level of precision equal to 1 μ strain and 0.1 °C. Several sensing cables are designed with different materials targeting to last for decades, either embedded in the concrete or attached to the surface of the structure. They must ensure an optimal transfer of temperature and strain from the concrete matrix to the optical fiber. Based on the European guide FD CEN/TR 14748 "Non-destructive testing - Methodology for qualification of non-destructive tests", a qualification method was developed. Tests were carried out using various sensing cables embedded in the volume or fixed to the surface of plain concrete specimens and representative-scale reinforced concrete structural elements. Measurements were performed with an OFDR instrument, while mechanical solicitations were imposed to the concrete element. Preliminary experiments seem very promising since measurements performed with distributed sensing systems are found comparable to values obtained with conventional sensors used in civil engineering and with the Strength of Materials Modelling. Moreover, the distributed sensing system makes it possible to detect and localize cracks appearing in concrete during the mechanical loading.

Application of operating experience in environmental qualification program

International Nuclear Information System (INIS)

Lee, S.Y.; Wise, R.

2000-01-01

Environmental qualification (EQ) of equipment related to nuclear safety has been carried out in the nuclear community since the 70's. It started with electrical equipment and then expanded to include mechanical equipment. During this evolutionary process, the methods used for EQ have gone through a long period of refinement and clarification. Prior to 1971, qualification for equipment in licensed nuclear power plants was based on the use of electrical components of commonly accepted high industrial quality without the benefit of specific environmental qualification standards. Between 1971 and 1974, most plants used the criteria of IEEE Standard 323-1971 as the basis for demonstrating qualification. Also during this period related 'daughter' standards, mainly by IEEE, became available which addressed qualification for specific equipment items. After July 1974, plants were required to meet the more comprehensive guidelines specified in IEEE Standard 323-1974 and the related 'daughter' standards. IEEE Standard 323-1974 later evolved into IEEE Standard 323-1983. For nuclear power plants built in Ontario during the 70's, i.e. Pickering B and Bruce B, has included the environmental qualification requirements in their respective nuclear safety design guides. It is now recognized that they are not up to the current EQ standards. Darlington, constructed during the 80's, implemented the environmental qualification program in its project. An Environmental Qualification (EQ) Program is now under way in Ontario Power Generation (OPG) to formally implement the Environmental Qualification for Bruce B, Pickering B, and Pickering A and to preserve the Qualification for Darlington G.S. This paper makes a thorough a review of the standard methods used in the past by utilities for environmental qualification. These methods include type testing, analysis, and operating experience. Both type testing and analysis have been clearly defined in standards listed in References [2] to [6] and

Development Of A Macro-Batch Qualification Strategy For The Hanford Tank Waste Treatment And Immobilization Plant

International Nuclear Information System (INIS)

Herman, Connie C.

2013-01-01

following: Collection and characterization of samples for relevant process analytes from the tanks to be blended during the staging process; Initiation of qualification activities earlier in the staging process to optimize the campaign composition through evaluation from both a processing and glass composition perspective; Definition of the parameters that are important for processing in the WTP facilities (unit operations) across the anticipated range of wastes and as they relate to qualification-scale equipment; Performance of limited testing with simulants ahead of the waste feed qualification sample demonstration as needed to determine the available processing window for that campaign; and Demonstration of sufficient mixing in the staging tank to show that the waste qualification sample chemical and physical properties are representative of the transfers to be made to WTP. Potential flowcharts for derivatives of the Hanford waste feed qualification process are also provided in this report. While these recommendations are an extension of the existing WTP waste qualification program, they are more in line with the processes currently performed for SRS. The implementation of these processes at SRS has been shown to offer flexibility for processing, having identified potential processing issues ahead of the qualification or facility processing, and having provided opportunity to optimize waste loading and throughput in the DWPF

Qualification tests for a dosimetry system

International Nuclear Information System (INIS)

Anon.

2005-01-01

The report of qualification tests for personnel dosemeters is detailed. Qualification test for the energy response and the incidence angle is given. The procedure of test is resumed. Different coefficients of conversion used in these tests are given in tables. (N.C.)

48 CFR 253.209 - Contractor qualifications.

Science.gov (United States)

2010-10-01

... 48 Federal Acquisition Regulations System 3 2010-10-01 2010-10-01 false Contractor qualifications. 253.209 Section 253.209 Federal Acquisition Regulations System DEFENSE ACQUISITION REGULATIONS SYSTEM, DEPARTMENT OF DEFENSE CLAUSES AND FORMS FORMS Prescription of Forms 253.209 Contractor qualifications. ...

Seismic qualification of equipment in operating nuclear power plants: Unresolved Safety Issue A-46

International Nuclear Information System (INIS)

Chang, T.Y.

1987-02-01

The margin of safety provided in existing nuclear power plant equipment to resist seismically induced loads and perform their intended safety functions may vary considerably, because of significant changes in design criteria and methods for the seismic qualification of equipment over the years. Therefore, the seismic qualification of equipment in operating plants must be reassessed to determine whether requalification is necessary. The objective of technical studies performed under the Task Action Plan A-46 was to establish an explicit set of guidelines and acceptance criteria to judge the adequacy of equipment under seismic loading at all operating plants, in lieu of requiring qualification to the current criteria that are applied to new plants. This report summarizes the work accomplished on USI A-46. In addition, the collection and review of seismic experience data and existing seismic test data are presented. Staff assessment of work accomplished under USI A-46 leads to the conclusion that the use of seismic experience data provides the most reasonable alternative to current qualification criteria. Consideration of seismic qualification by use of experience data was a specific task in USI A-46. Several other A-46 tasks serve to support the use of an experienced data base. The principal technical finding of USI A-46 is that seismic experience data, supplemented by existing seismic test data, applied in accordance with the guidelines developed, can be used to verify the seismic adequacy of mechanical and electrical equipment in operating nuclear plants. Explicit seismic qualification should be required only if seismic experience data or existing test data on similar components cannot be shown to apply

Requirements for qualification of manufacture of the ITER Central Solenoid and Correction Coils

Energy Technology Data Exchange (ETDEWEB)

Libeyre, Paul, E-mail: paul.libeyre@iter.org [ITER Organization, Route de Vinon sur Verdon, 13115 St Paul lez Durance (France); Li, Hongwei [ITER China, 15B Fuxing Road, Beijing 100862 (China); Reiersen, Wayne [US ITER Project Office, 1055 Commerce Park Dr., Oak Ridge, TN 37831 (United States); Dolgetta, Nello; Jong, Cornelis; Lyraud, Charles; Mitchell, Neil; Laurenti, Adamo [ITER Organization, Route de Vinon sur Verdon, 13115 St Paul lez Durance (France); Sgobba, Stefano [CERN, CH-1211 Genève 23 (Switzerland); Turck, Bernard [ITER Organization, Route de Vinon sur Verdon, 13115 St Paul lez Durance (France); Martovetsky, Nicolai; Everitt, David; Freudenberg, K.; Litherland, Steve; Rosenblad, Peter [US ITER Project Office, 1055 Commerce Park Dr., Oak Ridge, TN 37831 (United States); Smith, John; Spitzer, Jeff [General Atomics, P.O. Box 85608, San Diego, CA 92186-5608 (United States); Wei, Jing; Dong, Xiaoyu; Fang, Chao [ASIPP, Shushan Hu Road 350, Hefei, Anhui 230031 (China); and others

2015-10-15

Highlights: • A manufacturing line is installed for the ITER Correction Coils. • A manufacturing line is under installation for the ITER Central Solenoid. • Qualification of the manufacturing procedures has started for both manufacturing lines and acceptance criteria set. • Winding procedure of Correction Coils is qualified. - Abstract: The manufacturing line of the ITER Correction Coils (CC) at ASIPP in Hefei (China) was completed in 2013 and the manufacturing line of the ITER Central Solenoid (CS) modules is under installation at General Atomic premises in Poway (USA). In both cases, before starting production of the first coils, qualification of the manufacturing procedures is achieved by the construction of a set of mock-ups and prototypes to demonstrate that design requirements defined by the ITER Organization are effectively met. For each qualification item, the corresponding mock-ups are presented with the tests to be performed and the related acceptance criteria. The first qualification results are discussed.

Romanian-Canadian joint program for qualification of FCN as a CANDU fuel supplier

International Nuclear Information System (INIS)

Galeriu, C.A.; Andrei, G.; Bailescu, A.

1995-01-01

RENEL (Romania Power Authority), the co-ordinator of Romanian Nuclear Program, have decided to improve, starting 1990 the existing capability to produce CANDU nuclear fuel at FCN Pitesti. The objective of the program was defined with AAC (AECL - ANSALDO Consortium) for the qualification of FCN fuel plant according to Canadian Z299.2 standard. The Qualification Program was performed under AAC Work Order C-003. The co-ordination was assumed by AECL, as overall Design Authority. ZPI (Zircatec Precision Industries Inc., Canada), were designated to supply technical assistance, equipments and know how where necessary. After a preliminary verification of the FCN fuel plant, including the processes and system investigation, performed under AECL and ZPI assistance, the Qualification Program was defined in all details. The upgrading of documentation on all aspects required by Z299.2 was performed. Few processes needed to be reconsidered and equipment was delivered by ZPI or other suppliers. This includes mainly welding equipments and special inspection equipments. Health Physics was practically fully reconsidered. New equipment and practice were adapted to provide adequate control on health conditions. Every manufacturing and inspection process was checked to determine their performance during a Qualification Run based on acceptance criteria which have been established in the Qualification Plan. Manufacturing Demonstration Run was an important step to prove that all plant functions have been accomplished during the fabrication of 200 fuel bundles. These bundles have been fully accepted and 66 of them have been loaded in the first charge of Unit 1 Cemavoda NPS. The surveillance and audit actions made by AECL and ZPI during this period confirmed the FCN capability to operate an adequate system meeting the to required quality assurance standard. The very open attitude of AECL, Zircatec and FCN staff have stimulated the progress of the project and a successful achievement of the

Effects of Gas Turbine Component Performance on Engine and Rotary Wing Vehicle Size and Performance

Science.gov (United States)

Snyder, Christopher A.; Thurman, Douglas R.

2010-01-01

In support of the Fundamental Aeronautics Program, Subsonic Rotary Wing Project, further gas turbine engine studies have been performed to quantify the effects of advanced gas turbine technologies on engine weight and fuel efficiency and the subsequent effects on a civilian rotary wing vehicle size and mission fuel. The Large Civil Tiltrotor (LCTR) vehicle and mission and a previous gas turbine engine study will be discussed as a starting point for this effort. Methodology used to assess effects of different compressor and turbine component performance on engine size, weight and fuel efficiency will be presented. A process to relate engine performance to overall LCTR vehicle size and fuel use will also be given. Technology assumptions and levels of performance used in this analysis for the compressor and turbine components performances will be discussed. Optimum cycles (in terms of power specific fuel consumption) will be determined with subsequent engine weight analysis. The combination of engine weight and specific fuel consumption will be used to estimate their effect on the overall LCTR vehicle size and mission fuel usage. All results will be summarized to help suggest which component performance areas have the most effect on the overall mission.

Examination of a Junction-Box Adhesion Test for Use in Photovoltaic Module Qualification: Preprint

Energy Technology Data Exchange (ETDEWEB)

Miller, D. C.; Wohlgemuth, J. H.

2012-08-01

Engineering robust adhesion of the junction-box (j-box) is a hurdle typically encountered by photovoltaic (PV) module manufacturers during product development. There are historical incidences of adverse effects (e.g., fires) caused when the j-box/adhesive/module system has failed in the field. The addition of a weight to the j-box during the 'damp heat' IEC qualification test is proposed to verify the basic robustness of its adhesion system. The details of the proposed test will be described, in addition to the preliminary results obtained using representative materials and components. The described discovery experiments examine moisture-cured silicone, foam tape, and hot-melt adhesives used in conjunction with PET or glass module 'substrates.' To be able to interpret the results, a set of material-level characterizations was performed, including thermogravimetric analysis, differential scanning calorimetry, and dynamic mechanical analysis. PV j-boxes were adhered to a substrate, loaded with a prescribed weight, and then placed inside an environmental chamber (at 85C, 85% relative humidity). Some systems did not remain attached through the discovery experiments. Observed failure modes include delamination (at the j-box/adhesive or adhesive/substrate interface) and phase change/creep. The results are discussed in the context of the application requirements, in addition to the plan for the formal experiment supporting the proposed modification to the qualification test.

Similarity principles for equipment qualification by experience

International Nuclear Information System (INIS)

Kana, D.D.; Pomerening, D.J.

1988-07-01

A methodology is developed for seismic qualification of nuclear plant equipment by applying similarity principles to existing experience data. Experience data are available from previous qualifications by analysis or testing, or from actual earthquake events. Similarity principles are defined in terms of excitation, equipment physical characteristics, and equipment response. Physical similarity is further defined in terms of a critical transfer function for response at a location on a primary structure, whose response can be assumed directly related to ultimate fragility of the item under elevated levels of excitation. Procedures are developed for combining experience data into composite specifications for qualification of equipment that can be shown to be physically similar to the reference equipment. Other procedures are developed for extending qualifications beyond the original specifications under certain conditions. Some examples for application of the procedures and verification of them are given for certain cases that can be approximated by a two degree of freedom simple primary/secondary system. Other examples are based on use of actual test data available from previous qualifications. Relationships of the developments with other previously-published methods are discussed. The developments are intended to elaborate on the rather broad revised guidelines developed by the IEEE 344 Standards Committee for equipment qualification in new nuclear plants. However, the results also contribute to filling a gap that exists between the IEEE 344 methodology and that previously developed by the Seismic Qualification Utilities Group. The relationship of the results to safety margin methodology is also discussed. (author)

Improving engineers' performance with computers

International Nuclear Information System (INIS)

Purvis, E.E. III

1984-01-01

The problem addressed is how to improve the performance of engineers in the design, operation, and maintenance of nuclear power plants. The application of computer science to this problem offers a challenge in maximizing the use of developments outside the nuclear industry and setting priorities to address the most fruitful areas first. Areas of potential benefits include data base management through design, analysis, procurement, construction, operation maintenance, cost, schedule and interface control and planning, and quality engineering on specifications, inspection, and training

Current activities and challenges of the European network for inspection and qualification (ENIQ)

Energy Technology Data Exchange (ETDEWEB)

Martin, Oliver [European Commission, Joint Research Centre (JRC), Petten (Netherlands). Institute for Energy and Transport (IET); Martin, Etienne [EDF, St Denis (France). Direction Production Ingenierie; Booler, Russ [AMEC Clean Energy Europe, Warrington (United Kingdom); Zetterwall, Tommy [Swedish Qualification Centre, Taeby (Sweden); Walker, Tony [Rolls-Royce Submarines, Derby (United Kingdom)

2014-10-15

This article describes the development of the European Network for Inspection and Qualification (ENIQ) since the previous presentation of the network in the 2011 April/May edition of this journal, covering mainly the new technical challenges facing the network and resulting projects as well as the establishment of the new Task Group for Inspection Qualification Bodies. ENIQ is a utility-driven network dealing with the reliability and effectiveness of non-destructive testing (NDT) for nuclear power plants (NPP). ENIQ is recognised as one of the main contributors to today's global qualification codes and guidelines for in-service inspection (ISI) and has published nearly 50 documents. Among them are the 'European Methodology for Qualification of Non-Destructive Testing', the first qualification methodology based on technical justifications, the 'European Framework Document for Risk-Informed In-Service Inspection (RI-ISI)', and various recommend practices. In addition ENIQ has carried out two pilot studies and a number of surveys. In 2012, ENIQ joined the European based R and D association on Gen II and III reactors, NUGENIA, making ENIQ its 8{sup th} technical area. Following the entry into NUGENIA, ENIQ members have updated the ENIQ roadmap and included a number of new technical challenges facing its members in the near future. Also ENIQ established a third task group in 2013, the Task Group for Inspection Qualification Bodies (TGIQB), which should serve as an exchange forum for inspection qualification bodies. ENIQ is currently preparing or performing new projects and studies to tackle these challenges and new recommended practices and reports are likely to evolve from these projects, which will enable ENIQ to maintain its role as one of the main contributors to today's global qualification codes and guidelines for ISI.

Current activities and challenges of the European network for inspection and qualification (ENIQ)

International Nuclear Information System (INIS)

Martin, Oliver; Martin, Etienne; Zetterwall, Tommy; Walker, Tony

2014-01-01

This article describes the development of the European Network for Inspection and Qualification (ENIQ) since the previous presentation of the network in the 2011 April/May edition of this journal, covering mainly the new technical challenges facing the network and resulting projects as well as the establishment of the new Task Group for Inspection Qualification Bodies. ENIQ is a utility-driven network dealing with the reliability and effectiveness of non-destructive testing (NDT) for nuclear power plants (NPP). ENIQ is recognised as one of the main contributors to today's global qualification codes and guidelines for in-service inspection (ISI) and has published nearly 50 documents. Among them are the 'European Methodology for Qualification of Non-Destructive Testing', the first qualification methodology based on technical justifications, the 'European Framework Document for Risk-Informed In-Service Inspection (RI-ISI)', and various recommend practices. In addition ENIQ has carried out two pilot studies and a number of surveys. In 2012, ENIQ joined the European based R and D association on Gen II and III reactors, NUGENIA, making ENIQ its 8 th technical area. Following the entry into NUGENIA, ENIQ members have updated the ENIQ roadmap and included a number of new technical challenges facing its members in the near future. Also ENIQ established a third task group in 2013, the Task Group for Inspection Qualification Bodies (TGIQB), which should serve as an exchange forum for inspection qualification bodies. ENIQ is currently preparing or performing new projects and studies to tackle these challenges and new recommended practices and reports are likely to evolve from these projects, which will enable ENIQ to maintain its role as one of the main contributors to today's global qualification codes and guidelines for ISI.

Total qualification of class 1E electric equipment

International Nuclear Information System (INIS)

Chauvin, G.

1982-09-01

For nuclear power plant projects in France, Framatome and its partners Electricite de France (EDF) and the Commissariat a l'Energie Atomique (CEA) have responded to the present qualification context by implementing a wide-ranging qualification program to acquire significant organizational and practical experience. The following sections detail Framatome's approach to the activities of an organization mandated to provide a complete spectrum of qualification services. Thorough implementation of a Class 1E electric equipment qualification program by the competent organization or qualifier entails completion of three consecutive steps: 1) program preparation, 2) program implementation, and 3) analysis of test results and conclusion. The qualifier assumes extensive responsibility for each of these steps. The following sections present test facilities used in France to conduct a total qualification program for Class 1E electric equipment

Qualification criteria for persons responsible for radiation protection

International Nuclear Information System (INIS)

Wehner, G

1980-01-01

A survey of the qualification criteria included in the German atomic law (Atomic Energy Act, Radiological Protection Ordinance and X-ray Protection Ordinance) for persons responsible for radiation protection is given. Especially the various activities for which a health physics officer is required, the range of qualification in each case and the way the qualification has to be proved, are pointed out. Also the different guides that are issued to complete the legal requirements are mentioned. The definitions of the term qualification for health physics given in the different guides are cited and it is shown, that the qualification of a healt physics officer has to be based on the three criteria (I) vocational training. (II) professional experience and (III) the necessary knowledge in radiation protection. (orig./HP) [de

The qualification of reactor operators

International Nuclear Information System (INIS)

Lima, J.M. de; Soares, H.V.

1981-01-01

The qualification and performance of nuclear power personnel have an important influence on the availability and safety operation of these plants. This paper describes the Brazilian rules and norms established by the CNEN-Brazilian Atomic Energy Comission, as well as policy of other countries concerning training requirements and experiences of nuclear power reactor operators. Some coments are made about the im pact of the march 1979 Three Mile Island accident on upgrading the reactor training requirements in U.S.A. and its international implication. (Author) [pt

Performance Evaluation of an Experimental Turbojet Engine

Science.gov (United States)

Ekici, Selcuk; Sohret, Yasin; Coban, Kahraman; Altuntas, Onder; Karakoc, T. Hikmet

2017-11-01

An exergy analysis is presented including design parameters and performance assessment, by identifying the losses and efficiency of a gas turbine engine. The aim of this paper is to determine the performance of a small turbojet engine with an exergetic analysis based on test data. Experimental data from testing was collected at full-load of small turbojet engine. The turbojet engine exhaust data contains CO2, CO, CH4, H2, H2O, NO, NO2, N2 and O2 with a relative humidity of 35 % for the ambient air of the performed experiments. The evaluated main components of the turbojet engine are the air compressor, the combustion chamber and the gas turbine. As a result of the thermodynamic analysis, exergy efficiencies (based on product/fuel) of the air compressor, the combustion chamber and the gas turbine are 81.57 %, 50.13 % and 97.81 %, respectively. A major proportion of the total exergy destruction was found for the combustion chamber at 167.33 kW. The exergy destruction rates are 8.20 %, 90.70 % and 1.08 % in the compressor, the combustion chamber and the gas turbine, respectively. The rates of exergy destruction within the system components are compared on the basis of the exergy rate of the fuel provided to the engine. Eventually, the exergy rate of the fuel is calculated to be 4.50 % of unusable due to exergy destruction within the compressor, 49.76 % unusable due to exergy destruction within the combustion chamber and 0.59 % unusable due to exergy destruction within the gas turbine. It can be stated that approximately 55 % of the exergy rate of the fuel provided to the engine can not be used by the engine.

U-Mo fuel qualification program in HANARO

International Nuclear Information System (INIS)

Lee, K.H.; Lee, C.S.; Kim, H.R.; Kuk, I.H.; Kim, C.K.

2000-01-01

Atomized U-Mo fuel has shown good performance from the results of previous out-of-pile tests and post-irradiation examinations. A qualification program of rod type U-Mo fuel is in progress and the fuel will be irradiated in HANARO. 6 gU/cm 3 U-7Mo, U-8Mo and U-9Mo are considered in this program. The laboratory test results of porosity, mechanical property, thermal conductivity, and thermal compatibility test are discussed in this paper. In parallel with this qualification program, the feasibility study on the core conversion from the present U 3 Si fuel to U-Mo in HANARO will be initiated to provide technical bases for the policy making. Several options of core conversion for HANARO are proposed and each option will be addressed briefly in terms of the operation policy, fuel management, and licensing of HANARO. (author)

IPEJ's Role and Responsibility on Engineering Ethics Education

Science.gov (United States)

Taki, Shigeatsu

IPEJ (The Institution of Professional Engineers, Japan) is the representing engineering association of Japan organized under the Professional Engineer Law. Its role is to render services with respect to training to the professional engineers, guidance and communication of members in order to contribute maintaining their dignity, improving competence and advancing engineering practice. In 2000, the PE Law was amended substantially, then, IPEJ's activities are now enlarging. Those activities are concentrating into assistance to IPD for the Engineers-in-Training in view of engineering ethics, guidance to CPD for the Professional Engineers, and acceleration of capacity building for PE's as global engineers through the framework of international mutual recognition of qualifications.

High Temperature Materials Interim Data Qualification Report

International Nuclear Information System (INIS)

Lybeck, Nancy

2010-01-01

Projects for the very high temperature reactor (VHTR) Technology Development Office provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR program has established the NGNP Data Management and Analysis System (NDMAS) to ensure that VHTR data are qualified for use, stored in a readily accessible electronic form, and analyzed to extract useful results. This document focuses on the first NDMAS objective. It describes the High Temperature Materials characterization data stream, the processing of these data within NDMAS, and reports the interim FY2010 qualification status of the data. Data qualification activities within NDMAS for specific types of data are determined by the data qualification category assigned by the data generator. The High Temperature Materials data are being collected under NQA-1 guidelines, and will be qualified data. For NQA-1 qualified data, the qualification activities include: (1) capture testing, to confirm that the data stored within NDMAS are identical to the raw data supplied, (2) accuracy testing to confirm that the data are an accurate representation of the system or object being measured, and (3) documenting that the data were collected under an NQA-1 or equivalent Quality Assurance program. Currently, data from two test series within the High Temperature Materials data stream have been entered into the NDMAS vault: (1) Tensile Tests for Sm (i.e., Allowable Stress) Confirmatory Testing - 1,403,994 records have been inserted into the NDMAS database. Capture testing is in process. (2) Creep-Fatigue Testing to Support Determination of Creep-Fatigue Interaction Diagram - 918,854 records have been processed and inserted into the NDMAS database. Capture testing is in process.

Engine performance and emissions using Jatropha curcas, Ceiba pentandra and Calophyllum inophyllum biodiesel in a CI diesel engine

International Nuclear Information System (INIS)

Ong, Hwai Chyuan; Masjuki, H.H.; Mahlia, T.M.I.; Silitonga, A.S.; Chong, W.T.; Yusaf, Talal

2014-01-01

Biodiesel is a recognized replacement for diesel fuel in compressed ignition engines due to its significant environmental benefits. The purpose of this study is to investigate the engine performance and emissions produced from Jatropha curcas, Ceiba pentandra and Calophyllum inophyllum biodiesel in compressed ignition engine. The biodiesel production process and properties are discussed and a comparison of the three biodiesels as well as diesel fuel is undertaken. After that, engine performance and emissions testing was conducted using biodiesel blends 10%, 20%, 30% and 50% in a diesel engine at full throttle load. The engine performance shows that those biodiesel blends are suitable for use in diesel engines. A 10% biodiesel blend shows the best engine performance in terms of engine torque, engine power, fuel consumption and brake thermal efficiency among the all blending ratios for the three biodiesel blends. Biodiesel blends have also shown a significant reduction in CO 2 , CO and smoke opacity with a slight increase in NO x emissions. - Highlights: • The properties of JCME, CPME and CIME fulfill ASTM standard. • Engine performance and emission was conducted for JCME, CPME and CIME. • The B10 is the best engine performance and reduce in exhaust emission

Skill qualifications in pediatric minimally invasive surgery.

Science.gov (United States)

Iwanaka, Tadashi; Morikawa, Yasuhide; Yamataka, Atsuyuki; Nio, Masaki; Segawa, Osamu; Kawashima, Hiroshi; Sato, Masahito; Terakura, Hirotsugu; Take, Hiroshi; Hirose, Ryuichiro; Yagi, Makoto

2011-07-01

In 2006, The Japanese Society of Pediatric Endoscopic Surgeons devised a plan to develop a pediatric endoscopic surgical skill qualification (ESSQ) system. This system is controlled by The Japan Society for Endoscopic Surgery. The standard requirement for skills qualification is the ability of each applicant to complete common types of laparoscopic surgery. The main goal of the system is to decrease complications of laparoscopic surgery by evaluating the surgical skills of each applicant and subsequently certify surgeons with adequate skills to perform laparoscopic operations safely. A committee of pediatric ESSQ created a checklist to assess the applicant's laparoscopic surgical skills. Skills are assessed in a double-blinded fashion by evaluating an unedited video recording of a fundoplication for pediatric gastroesophageal reflux disease. The initial pediatric ESSQ system was started in 2008. In 2008 and 2009, respectively, 9 out of 17 (53%) and 6 out of 12 (50%) applicants were certified as expert pediatric laparoscopic surgeons. Our ultimate goal is to provide safe and appropriate pediatric minimally invasive procedures and to avoid severe complications. To prove the predictive validity of this system, a survey of the outcomes of operations performed by certified pediatric surgeons is required.

A Probabilistic Design Methodology for a Turboshaft Engine Overall Performance Analysis

Directory of Open Access Journals (Sweden)

Min Chen

2014-05-01

Full Text Available In reality, the cumulative effect of the many uncertainties in engine component performance may stack up to affect the engine overall performance. This paper aims to quantify the impact of uncertainty in engine component performance on the overall performance of a turboshaft engine based on Monte-Carlo probabilistic design method. A novel probabilistic model of turboshaft engine, consisting of a Monte-Carlo simulation generator, a traditional nonlinear turboshaft engine model, and a probability statistical model, was implemented to predict this impact. One of the fundamental results shown herein is that uncertainty in component performance has a significant impact on the engine overall performance prediction. This paper also shows that, taking into consideration the uncertainties in component performance, the turbine entry temperature and overall pressure ratio based on the probabilistic design method should increase by 0.76% and 8.33%, respectively, compared with the ones of deterministic design method. The comparison shows that the probabilistic approach provides a more credible and reliable way to assign the design space for a target engine overall performance.

Commercial Parts Technology Qualification Processes

Science.gov (United States)

Cooper, Mark S.

2013-01-01

Many high-reliability systems, including space systems, use selected commercial parts (including Plastic Encapsulated Microelectronics or PEMs) for unique functionality, small size, low weight, high mechanical shock resistance, and other factors. Predominantly this usage is subjected to certain 100% tests (typically called screens) and certain destructive tests usually (but not always) performed on the flight lot (typically called qualification tests). Frequently used approaches include those documented in EEE-INST-002 and JPL DocID62212 (which are sometimes modified by the particular aerospace space systems manufacturer). In this study, approaches from these documents and several space systems manufacturers are compared to approaches from a launch systems manufacturer (SpaceX), an implantable medical electronics manufacturer (Medtronics), and a high-reliability transport system process (automotive systems). In the conclusions section, these processes are outlined for all of these cases and presented in tabular form. Then some simple comparisons are made. In this introduction section, the PEM technology qualification process is described, as documented in EEE-INST-002 (written by the Goddard Space Flight Center, GSFC), as well as the somewhat modified approach employed at the Jet Propulsion Laboratory (JPL). Approaches used at several major NASA contractors are also described

Qualification Test for Korean Mockups of ITER Blanket First Wall

International Nuclear Information System (INIS)

Kim, S. K.; Lee, D. W.; Bae, Y. D.; Hong, B. G.; Jung, H. K.; Jung, Y. I.; Park, J. Y.; Jeong, Y. H.; Choi, B. K.; Kim, B. Y.

2009-01-01

ITER First Wall (FW) includes the beryllium armor tiles joined to CuCrZr heat sink with stainless steel cooling tubes. This first wall panels are one of the critical components in the ITER machine with the surface heat flux of 0.5 MW/m 2 or above. So qualification program needs to be performed with the goal to qualify the joining technologies required for the ITER First Wall. Based on the results of tests, the acceptance of the developed joining technologies will be established. The results of this qualification test will affect the final selection of the manufacturers for the ITER First Wall

Safety design guides for environmental qualification for CANDU 9

International Nuclear Information System (INIS)

Lee, Duk Su; Chang, Woo Hyun; Lee, Nam Young; A. C. D. Wright

1996-03-01

This safety design guide describes the safety philosophy and requirements for the environmental qualification of safety related systems and components for CANDU 9. The environmental qualification program identifies the equipments to be qualified and conditions to be used for qualification and provides comprehensive set of documentation to ensure that the qualification is complete and can be maintained for the life of the plant. A summary of the system, components and structures requiring environmental qualification is provided in the table for the guidance of the system design, and this table will be subject to change or confirmation by the environmental qualification program. Also, plant ares subject to harsh environment is provided in the figure. The change status of the regulatory requirements, code and standards should be traced and this safety design guide shall be updated accordingly. 1 tab., 5 figs. (Author) .new

THYC qualification on Vatican-1 low pressure tests

International Nuclear Information System (INIS)

Duval, C.; Guichard, J.

1991-06-01

PWR cores or fuel assemblies are components of a nuclear power plant involving single and two-phase flows in rod bundles. The knowledge of the detailed two-phase and three-dimensional flow patterns is necessary to evaluate the singularity (grids) and bypass effects on the Departure from Nucleate Boiling (DNB) in reactor cores during incidental transients. For that purpose, since 1989, the VATICAN experiment has been performed at EDF as a part of the qualification program of the three-dimensional computer code THYC, developed by EDF. The qualification strategy of the THYC software for PWR cores is the following: assuming the theoretical or experimental knowledge of regular and singular pressure drops and grid turbulence sources in single-phase, pressure drop multipliers and relative velocity in two-phase flow, the VATICAN experiment allows to evaluate the diffusion phenomena in two-phase flow. It provides thermalhydraulic measurements on a mock-up of a part of 900 MWe PWR fuel assembly in single and two-phase flows, with power and quality gradients. The first configuration of the mock-up, with simple spacer grids, is studied (VATICAN-1). The specific effects of mixing spacer grids will be compared to these data through a second configuration. The last void fraction measurements, using a γ-ray technique, performed on VATICAN-1 low pressure tests allowed to qualify a set of closure relations, particularly a model of little two-phase diffusion, adapted to two-phase flows at low pressure (5.0MPa). The qualification of subcooled boiling and diffusion models will continue on next VATICAN and other experimental campaigns [fr

WFIRST: Coronagraph Systems Engineering and Performance Budgets

Science.gov (United States)

Poberezhskiy, Ilya; cady, eric; Frerking, Margaret A.; Kern, Brian; Nemati, Bijan; Noecker, Martin; Seo, Byoung-Joon; Zhao, Feng; Zhou, Hanying

2018-01-01

The WFIRST coronagraph instrument (CGI) will be the first in-space coronagraph using active wavefront control to directly image and characterize mature exoplanets and zodiacal disks in reflected starlight. For CGI systems engineering, including requirements development, CGI performance is predicted using a hierarchy of performance budgets to estimate various noise components — spatial and temporal flux variations — that obscure exoplanet signals in direct imaging and spectroscopy configurations. These performance budgets are validated through a robust integrated modeling and testbed model validation efforts.We present the performance budgeting framework used by WFIRST for the flow-down of coronagraph science requirements, mission constraints, and observatory interfaces to measurable instrument engineering parameters.

IEEE 693 seismic qualification of composites for substation high-voltage equipment

Energy Technology Data Exchange (ETDEWEB)

Schiff, A.J. [Precision Measurement Instruments, Los Altos Hills, CA (United States); Kempner, L.Jr. [Bonneville Power Administration, Vancouver, BC (Canada)

2004-07-01

Standard 693-1997 of the Institute of Electrical and Electronic Engineers (IEEE) is the recommended practice for seismic design of substations. It represents a significant improvement in the way the power industry seismically qualifies substation high-voltage equipment. This paper described the use of IEEE Standard 693 for hollow-core composite insulators that are used on high-voltage transformers and demonstrated that changes are warranted. The following four failure modes associated with the composite insulator were discussed: bond degradation, bond failure, tube degradation and tube layer delamination. The authors evaluated the IEEE 693 qualification procedure of time history shake-table and static-pull tests and were concerned about acceptance criteria. It was shown that acceptance criteria are not valid for qualifying hollow-core composites and that static-pull tests are needed after the vibration qualification tests are completed. It was suggested that more research is warranted to determine if bonding at the top part of the flange can be eliminated, thereby eliminating bond degradation. The resulting increase in system damping would improve the dynamic response of the unit. 1 ref., 10 figs.

Equipment Qualification Data Base user manual

International Nuclear Information System (INIS)

Decker, Q.R.; Fackrell, L.J.; Fitch, L.R.; Meeky, O.B.

1985-09-01

This manual details the Equipment Qualification Data Base (EQDB), its usage, and contents. The EQDB consists of two files; the Plant Qualification File (PQF) and the Equipment Qualification File (EQF). The PQF contains plant specific environmental data and the EQF contains summaries of various test results. Two data management systems are used to manipulate the data and are discussed in this manual. SAS Institute System 2000 (S2K) is the management system for the PQF and Query Update (QU) is the operating system for the EQF. Each management system contains report writers. These writers and how to use them are discussed in detail in this manual

Solar array qualification through qualified analysis

Science.gov (United States)

Zijdemans, J.; Cruijssen, H. J.; Wijker, J. J.

1991-04-01

To achieve qualification is in general a very expensive exercise. For solar arrays this is done by a dedicated test program through which final qualification is achieved. Due to severe competition on the solar array market, cheaper means are looked for to achieve a qualified product for the customers. One of the methods is to drastically limit the environmental test program and to qualify the solar-array structure against its environmental loads by analysis. Qualification by analysis is possible. The benefits are that a significant amount of development effort can be saved in case such a powerful tool is available. Extensive testing can be avoided thus saving time and money.

Hydrogen engine performance analysis. First annual report

Energy Technology Data Exchange (ETDEWEB)

Adt, Jr., R. R.; Swain, M. R.; Pappas, J. M.

1978-08-01

Many problems associated with the design and development of hydrogen-air breathing internal combustion engines for automotive applications have been identified by various domestic and foreign researchers. This project addresses the problems identified in the literature, seeks to evaluate potential solutions to these problems, and will obtain and document a design data-base convering the performance, operational and emissions characteristics essential for making rational decisions regarding the selection and design of prototype hydrogen-fueled, airbreathing engines suitable for manufacture for general automotive use. Information is included on the operation, safety, emission, and cost characteristics of hydrogen engines, the selection of a test engine and testing facilities, and experimental results. Baseline data for throttled and unthrottled, carburetted, hydrogen engine configurations with and without exhaust gas recirculation and water injection are presented. In addition to basic data gathering concerning performance and emissions, the test program conducted was formulated to address in detail the two major problems that must be overcome if hydrogen-fueled engines are to become viable: flashback and comparatively high NO/sub x/ emissions at high loads. In addition, the results of other hydrogen engine investigators were adjusted, using accepted methods, in order to make comparisons with the results of the present study. The comparisons revealed no major conflicts. In fact, with a few exceptions, there was found to be very good agreement between the results of the various studies.

Rotary engine performance limits predicted by a zero-dimensional model

Science.gov (United States)

Bartrand, Timothy A.; Willis, Edward A.

1992-01-01

A parametric study was performed to determine the performance limits of a rotary combustion engine. This study shows how well increasing the combustion rate, insulating, and turbocharging increase brake power and decrease fuel consumption. Several generalizations can be made from the findings. First, it was shown that the fastest combustion rate is not necessarily the best combustion rate. Second, several engine insulation schemes were employed for a turbocharged engine. Performance improved only for a highly insulated engine. Finally, the variability of turbocompounding and the influence of exhaust port shape were calculated. Rotary engines performance was predicted by an improved zero-dimensional computer model based on a model developed at the Massachusetts Institute of Technology in the 1980's. Independent variables in the study include turbocharging, manifold pressures, wall thermal properties, leakage area, and exhaust port geometry. Additions to the computer programs since its results were last published include turbocharging, manifold modeling, and improved friction power loss calculation. The baseline engine for this study is a single rotor 650 cc direct-injection stratified-charge engine with aluminum housings and a stainless steel rotor. Engine maps are provided for the baseline and turbocharged versions of the engine.

Surveys on awareness and needs of industries to external accreditation system in engineer education; Gijutsusha kyoiku no gaibu ninteiseido donyu ni taisuru sangyo kai no ioshiki to needs ni kansuru chosa

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-03-01

In certifying the engineer educational programs at advanced educational organizations, questionnaire and visiting surveys were performed to identify the awareness and needs of industries, and reflect the results to the external accreditation system. The questionnaire survey was conducted on 1,100 engineers acting in the wide technical areas. Effective replies were obtained from 528 engineers. The visiting survey was executed on different business areas and operations. The result of the survey revealed that, in the awareness related to international universality of the engineer education and engineer qualification, 87% answered that they feel they need them, but the cognition rate on the accreditation system has not reached even 50%. In hearing the opinions from representatives in the industries, they indicated that it is not correct to link the certification course of JABEE directly to the engineer qualification; international applicability of JABEE with America is fine, but defining the engineers who desire to come from Asian countries and work in Japan is necessary; the engineer education has its importance shifting from quantity to quality and specialization, but on the other hand diversity is also demanded; and criteria would be necessary to guarantee the minimum required knowledge and capability. (NEDO)

Approach to customer qualification of the BNFL Sellafield Mox Plant

International Nuclear Information System (INIS)

Sullivan, P.

2003-01-01

BNFL started plutonium commissioning of its Sellafield MOX Plant (SMP) in December 2001, with the first MOX pellets being produced in May 2002. SMP was designed to manufacture a range of both PWR and BWR fuel types for a number of different customers. During commissioning and early MOX fuel manufacturing BNFL has been demonstrating its ability to both automatically manufacture and inspect MOX fuel to meet the requirements of different customers' specifications and fuel types. The qualification project consisted of common and project specific qualification. Common qualification was carried out to demonstrate BNFL could meet several customers' requirements during the same qualification test. Project specific qualification was carried out for one customer only as the fabrication or inspection equipment was specific to their fuel type. An example is the fuel assembly process. The reasons for BNFL carrying out common qualification were: - Develop a common qualified process to meet different customer specifications. - Minimise future qualifications prior to starting future fuel campaigns. - Ensure BNFL understands and effectively manages different customer requirements in SMP. BNFL has approached qualification of SMP systematically. Firstly the inspection system was qualified, and once completed the inspection system was then used in the qualification of the manufacturing process. (orig.)

Lean mixture engine testing and evaluation program. [for automobile engine pollution and fuel performances

Science.gov (United States)

Dowdy, M. W.; Hoehn, F. W.; Griffin, D. C.

1975-01-01

Experimental results for fuel consumption and emissions are presented for a 350 CID (5.7 liter) Chevrolet V-8 engine modified for lean operation with gasoline. The lean burn engine achieved peak thermal efficiency at an equivalence ratio of 0.75 and a spark advance of 60 deg BTDC. At this condition the lean burn engine demonstrated a 10% reduction in brake specific fuel consumption compared with the stock engine; however, NOx and hydrocarbon emissions were higher. With the use of spark retard and/or slightly lower equivalence ratios, the NOx emissions performance of the stock engine was matched while showing a 6% reduction in brake specific fuel consumption. Hydrocarbon emissions exceeded the stock values in all cases. Diagnostic data indicate that lean performance in the engine configuration tested is limited by ignition delay, cycle-to-cycle pressure variations, and cylinder-to-cylinder distribution.

49 CFR 214.351 - Training and qualification of flagmen.

Science.gov (United States)

2010-10-01

... 49 Transportation 4 2010-10-01 2010-10-01 false Training and qualification of flagmen. 214.351... ADMINISTRATION, DEPARTMENT OF TRANSPORTATION RAILROAD WORKPLACE SAFETY Roadway Worker Protection § 214.351 Training and qualification of flagmen. (a) The training and qualification for roadway workers assigned the...

40 CFR 62.14595 - What are the operator training and qualification requirements?

Science.gov (United States)

2010-07-01

... control equipment and factors affecting performance (where applicable). (vi) Inspection and maintenance of... Commenced Construction On or Before November 30, 1999 Operator Training and Qualification § 62.14595 What...

ITER tungsten divertor design development and qualification program

Energy Technology Data Exchange (ETDEWEB)

Hirai, T., E-mail: takeshi.hirai@iter.org [ITER Organization, Route de Vinon sur Verdon, F-13115 Saint Paul lez Durance (France); Escourbiac, F.; Carpentier-Chouchana, S.; Fedosov, A.; Ferrand, L.; Jokinen, T.; Komarov, V.; Kukushkin, A.; Merola, M.; Mitteau, R.; Pitts, R.A.; Shu, W.; Sugihara, M. [ITER Organization, Route de Vinon sur Verdon, F-13115 Saint Paul lez Durance (France); Riccardi, B. [F4E, c/ Josep Pla, n.2, Torres Diagonal Litoral, Edificio B3, E-08019 Barcelona (Spain); Suzuki, S. [JAEA, Fusion Research and Development Directorate JAEA, 801-1 Mukouyama, Naka, Ibaragi 311-0193 (Japan); Villari, R. [Associazione EURATOM-ENEA sulla Fusione, Via Enrico Fermi 45, I-00044 Frascati, Rome (Italy)

2013-10-15

Highlights: • Detailed design development plan for the ITER tungsten divertor. • Latest status of the ITER tungsten divertor design. • Brief overview of qualification program for the ITER tungsten divertor and status of R and D activity. -- Abstract: In November 2011, the ITER Council has endorsed the recommendation that a period of up to 2 years be set to develop a full-tungsten divertor design and accelerate technology qualification in view of a possible decision to start operation with a divertor having a full-tungsten plasma-facing surface. To ensure a solid foundation for such a decision, a full tungsten divertor design, together with a demonstration of the necessary high performance tungsten monoblock technology should be completed within the required timescale. The status of both the design and technology R and D activity is summarized in this paper.

Engine Performance Test of the 1975 Chrysler - Nissan Model CN633 Diesel Engine

Science.gov (United States)

1975-09-01

An engine test of the Chrysler-Nissan Model CN633 diesel engine was performed to determine its steady-state fuel consumption and emissions (HC, CO, NOx) maps. The data acquired are summarized in this report.

On safety 1E qualification of electrical equipment for nuclear power stations

International Nuclear Information System (INIS)

Segarceanu, D.; Geambasu, C.; Avramescu, M.

1995-01-01

Electrical equipment and systems for the emergency shutdown of a nuclear reactor are qualified according to safety class 1E. Methods of qualification meeting the requirements should be used, either individually or in combination include, type-test qualification, qualification by operating experience, qualification by analysis, combined qualification. These methods qualification principles, procedures and documents are discussed. (N.T.). 1 fig

Performance and emission of CI engine fuelled with camelina sativa oil

International Nuclear Information System (INIS)

Kruczyński, Stanisław W.

2013-01-01

Highlights: ► Camelina sativa as a potential source of alternative fuel. ► Neat camelina sativa oil as a fuel for CI engine. ► The engine performance and emissions of CI engine fuelled with neat camelina sativa oil. ► Comparison of rate of heat release for camelina sativa oil and diesel oil. - Abstract: The paper describes the results of the tests of CI Perkins 1104C-44 engine fuelled with camelina sativa oil. The engine was not especially calibrated for fuelling with the vegetable fuel. During the test the engine performance and emissions were analysed. For comparison the same speed characteristic was examined for standard fuelling of the engine with diesel oil. In order to understand the engine performance and emission the mass fraction burnt and the rate of heat release was calculated and compared for the same energy provided to the engine cylinder with the injected fuels. The results show that there is possible to receive relatively good engine performance for fuelling the engine with camelina sativa oil but there is a need to change the calibration parameters of the engine fuel system when the engine is fuelled with this fuel.

Performance and combustion characteristics of direct-injection stratified-charge rotary engines

Science.gov (United States)

Nguyen, Hung Lee

1987-01-01

Computer simulations of the direct-injection stratified-charge (DISC) Wankel engine have been used to calculate heat release rates and performance and efficiency characteristics of the 1007R engine. Engine pressure data have been used in a heat release analysis to study the effects of heat transfer, leakage, and crevice flows. Predicted engine performance data are compared with experimental test data over a range of engine speeds and loads. An examination of methods to improve the performance of the Wankel engine with faster combustion, reduced leakage, higher compression ratio, and turbocharging is presented.

Predicted performance of an integrated modular engine system

Science.gov (United States)

Binder, Michael; Felder, James L.

1993-01-01

Space vehicle propulsion systems are traditionally comprised of a cluster of discrete engines, each with its own set of turbopumps, valves, and a thrust chamber. The Integrated Modular Engine (IME) concept proposes a vehicle propulsion system comprised of multiple turbopumps, valves, and thrust chambers which are all interconnected. The IME concept has potential advantages in fault-tolerance, weight, and operational efficiency compared with the traditional clustered engine configuration. The purpose of this study is to examine the steady-state performance of an IME system with various components removed to simulate fault conditions. An IME configuration for a hydrogen/oxygen expander cycle propulsion system with four sets of turbopumps and eight thrust chambers has been modeled using the Rocket Engine Transient Simulator (ROCETS) program. The nominal steady-state performance is simulated, as well as turbopump thrust chamber and duct failures. The impact of component failures on system performance is discussed in the context of the system's fault tolerant capabilities.

The Little Engines That Could: Modeling the Performance of World Wide Web Search Engines

OpenAIRE

Eric T. Bradlow; David C. Schmittlein

2000-01-01

This research examines the ability of six popular Web search engines, individually and collectively, to locate Web pages containing common marketing/management phrases. We propose and validate a model for search engine performance that is able to represent key patterns of coverage and overlap among the engines. The model enables us to estimate the typical additional benefit of using multiple search engines, depending on the particular set of engines being considered. It also provides an estim...

Device Engineering Towards Improved Tin Sulfide Solar Cell Performance and Performance Reproducibility

Energy Technology Data Exchange (ETDEWEB)

Steinmann, Vera; Chakraborty, Rupak; Rekemeyer, Paul; Siol, Sebastian; Martinot, Loic; Polizzotti, Alex; Yang, Chuanxi; Hartman, Katy; Gradecak, Silvija; Zakutayev, Andriy; Gordon, Roy G.; Buonassisi, Tonio

2016-11-21

As novel absorber materials are developed and screened for their photovoltaic (PV) properties, the challenge remains to rapidly test promising candidates in high-performing PV devices. There is a need to engineer new compatible device architectures, including the development of novel transparent conductive oxides and buffer layers. Here, we consider the two approaches of a substrate-style and a superstrate-style device architecture for novel thin-film solar cells. We use tin sulfide as a test absorber material. Upon device engineering, we demonstrate new approaches to improve device performance and performance reproducibility.

Guidelines for seismic qualification by experience in ALWRs

International Nuclear Information System (INIS)

Bandyopadhyay, K.K.

1994-01-01

The methodologies and acceptance criteria for seismic qualification of equipment are provided in IEEE Std. 344 endorsed by the Nuclear Regulatory Commission (NRC) in the Standard Review Plan. The IEEE Standard allows seismic qualification by use of the similarity analysis method. Data available from past earthquake events or vibration tests can be used in this regard. The nuclear industry has collected a vast amount of earthquake experience and test data in the last decade, and is planning to use it for seismic qualification of equipment in advanced light water reactor (ALWR) plants. This paper discusses the existing data bases including their limitations and describes the ways these data bases can be used for equipment qualification in ALWR plants

Guidelines for seismic qualification by experience in ALWRs

International Nuclear Information System (INIS)

Bandyopadhyay, K.K.

1993-01-01

The methodologies and acceptance criteria for seismic qualification of equipment are provided in IEEE Std. 344 endorsed by the Nuclear Regulatory Commission (NRC) in the Standard Review Plan. The IEEE Standard allows seismic qualification by use of the similarity analysis method. Data available from past earthquake events or vibration tests can be used in this regard. The nuclear industry has collected a vast amount of earthquake experience and test data in the last decade, and is planning to use it for seismic qualification of equipment in advanced light water reactor (ALWR) plants. This paper discusses the existing data bases including their limitations and describes the ways these data bases can be used for equipment qualification in ALWR plants

Safety review for seismic qualification on nuclear power plant equipment

International Nuclear Information System (INIS)

Fang Qingxian

1995-01-01

The standards and requirements for seismic qualification of nuclear power plant's component have been fully addressed, including the scope of seismic qualification, the approach and the method of common seismic qualification, the procedure of the seismic tests, and the criteria for the seismic qualification review. The problems discovered in the safety review and the solution for these problems and some other issues are also discussed

PROBLEMS OF COMPETENCY-BASED ASSESSMENT OF APPLIED QUALIFICATIONS

Directory of Open Access Journals (Sweden)

S. A. Efimova

2017-01-01

Full Text Available Introduction. The search of the unified tools of competences measurement of vocational training institutions graduates and identification of mechanisms of interrelation of these competences with requirements of professional standards imposed to workers of various levels are brought into focus in the context of formation of National system of qualifications of the Russian Federation, introduction of the Third-generation Federal State Educational Standards and transition of professional education to the modular, and competence-based model of the organization of training. The aim of the article is to justify the content, structure and technology of competency-based assessment, as a set of interrelated activities and regulated procedures performed on the basis of the standardized interdisciplinary evaluation materials. Methodology and research methods. The present investigation is based on systematic-activity and competency-based approaches, analysis, systematization, and generalization. Results. The place of competencies, as a part of educational outcomes of vocational education programs, is justified. Critical analysis of typical methodological solutions that are typical for the modern pedagogical practices of the competency-based assessment is performed. The content and organizational design of the process of competency-based assessment is described. Scientific novelty. The conceptual apparatus of competency-based assessment is supplemented with the «sub-competence» category - component of competence, which retains all of its properties due to human activities. Factors of objects choice and methods of assessment in identifying the professional competences are proved. Practical significance. Results of the study can be used by researchers involved with assessment procedures; methodologists and teachers of professional educational organizations, training institutes, independent centers of the qualifications evaluation for the organization of

Reaction Qualifications Revisited

DEFF Research Database (Denmark)

Lippert-Rasmussen, Kasper

2009-01-01

to a person's effectiveness by causing a favourable reaction in customers, co-workers etc. (for short: recipients) - are involved, this assumption is false. Building on work by Wertheimer, Mason, and Miller, this paper proposes an account of the reaction qualifications that count, from the point of view...... preferences, recipients should not respond to the applicant actually hired on the basis of their (the recipients') racial preferences. My account decomposes the meritocratic ideal into four separate norms, one of which applies to recipients rather than to selectors. Finally, it defends the view that reaction...... qualifications based on antimeritocratic reactions, while not unproblematic, are not entirely irrelevant from the point of view of merit. Notably, selectors need not discount them when no one - including the targets of the objectionable preferences - is unfairly disadvantaged. Because not all problematic...

QUALIFICATIONS FRAMEWORKS FOR LIFELONG LEARNING CONQUERING THE WORLD?

Directory of Open Access Journals (Sweden)

Arjen Deij

2014-01-01

Full Text Available The paper reveals the international prospects of developing and spreading the qualifications frameworks across the globe. It introduces the key terms and concepts related to the given issue, and examines both the benefits and challenges of qualifications frameworks implementation. The author looks into the origins and causes of the worldwide interest in qualifications framework application, and gives the overview of related recent publications and their conclusions to reinforce the provided argumentation.

BWR reactor water cleanup system flexible wedge gate isolation valve qualification and high energy flow interruption test

International Nuclear Information System (INIS)

DeWall, K.G.; Steele, R. Jr.

1989-10-01

This report presents the results of research performed to develop technical insights for the NRC effort regarding Generic Issue 87, ''Failure of HPCI Steam Line Without Isolation.'' Volume III of this report contains the data and findings from the original research performed to assess the qualification of the valves and reported in EGG-SSRE-7387, ''Qualification of Valve Assemblies in High Energy BWR Systems Penetrating Containment.'' We present the original work here to complete the documentation trail. The recommendations contained in Volume III of this report resulted in the test program described in Volume I and II. The research began with a survey to characterize the population of normally open containment isolation valves in those process lines that connect to the primary system and penetrate containment. The qualification methodology used by the various manufacturers identified in the survey is reviewed and deficiencies in that methodology are identified. Recommendations for expanding the qualification of valve assemblies for high energy pipe break conditions are presented. 11 refs., 1 fig., 2 tabs

Dynamic Performance of High Bypass Ratio Turbine Engines With Water Ingestion

Science.gov (United States)

Murthy, S. N. B.

1996-01-01

The research on dynamic performance of high bypass turbofan engines includes studies on inlets, turbomachinery and the total engine system operating with air-water mixture; the water may be in vapor, droplet, or film form, and their combinations. Prediction codes (WISGS, WINCOF, WINCOF-1, WINCLR, and Transient Engine Performance Code) for performance changes, as well as changes in blade-casing clearance, have been established and demonstrated in application to actual, generic engines. In view of the continuous changes in water distribution in turbomachinery, the performance of both components and the total engine system must be determined in a time-dependent mode; hence, the determination of clearance changes also requires a time-dependent approach. In general, the performance and clearances changes cannot be scaled either with respect to operating or ingestion conditions. Removal of water prior to phase change is the most effective means of avoiding ingestion effects. Sufficient background has been established to perform definitive, full scale tests on a set of components and a complete engine to establish engine control and operability with various air-water vapor-water mixtures.

A guide to qualification of electrical equipment for nuclear power plants. Final report, November 1983

International Nuclear Information System (INIS)

Marion, A.; Lamken, D.; Harrall, T.; Kasturi, S.; Holzman, P.; Carfagno, S.; Thompson, D.; Boyer, B.; Hanneman, H.; Rule, W.

1983-09-01

Equipment qualification demonstrates that nuclear power plant equipment can perform its safety function - that despite age or the adverse conditions of a design basis accident the equipment can work as needed. This report is a guide to the overall process of electrical equipment qualification. It should interest those who design such equipment, those who buy it, or test it, and even those who install and maintain it. (author)

Qualification of safety-related valve actuators

International Nuclear Information System (INIS)

Anon.

1981-01-01

This Standard describes the qualification of all types of power-driven valve actuators, including damper actuators, for safety-related functions in nuclear power generating stations. It may also be used to separately qualify actuator components. This Standard establishes the minimum requirements for, and guidance regarding, the methods and procedures for qualification of all safety-related functions of power-driven valve actuators

Qualification of software and hardware

International Nuclear Information System (INIS)

Gossner, S.; Schueller, H.; Gloee, G.

1987-01-01

The qualification of on-line process control equipment is subdivided into three areas: 1) materials and structural elements; 2) on-line process-control components and devices; 3) electrical systems (reactor protection and confinement system). Microprocessor-aided process-control equipment are difficult to verify for failure-free function owing to the complexity of the functional structures of the hardware and to the variety of the software feasible for microprocessors. Hence, qualification will make great demands on the inspecting expert. (DG) [de

48 CFR 1437.7001 - Contractor qualification requirements.

Science.gov (United States)

2010-10-01

... 48 Federal Acquisition Regulations System 5 2010-10-01 2010-10-01 false Contractor qualification requirements. 1437.7001 Section 1437.7001 Federal Acquisition Regulations System DEPARTMENT OF THE INTERIOR... Contractor qualification requirements. (a) Prior to award of a contract for real property appraisal services...

Design and Demonstration of Emergency Control Modes for Enhanced Engine Performance

Science.gov (United States)

Liu, Yuan; Litt, Jonathan S.; Guo, Ten-Huei

2013-01-01

A design concept is presented for developing control modes that enhance aircraft engine performance during emergency flight scenarios. The benefits of increased engine performance to overall vehicle survivability during these situations may outweigh the accompanied elevated risk of engine failure. The objective involves building control logic that can consistently increase engine performance beyond designed maximum levels based on an allowable heightened probability of failure. This concept is applied to two previously developed control modes: an overthrust mode that increases maximum engine thrust output and a faster response mode that improves thrust response to dynamic throttle commands. This paper describes the redesign of these control modes and presents simulation results demonstrating both enhanced engine performance and robust maintenance of the desired elevated risk level.

Performance of a supercharged direct-injection stratified-charge rotary combustion engine

Science.gov (United States)

Bartrand, Timothy A.; Willis, Edward A.

1990-01-01

A zero-dimensional thermodynamic performance computer model for direct-injection stratified-charge rotary combustion engines was modified and run for a single rotor supercharged engine. Operating conditions for the computer runs were a single boost pressure and a matrix of speeds, loads and engine materials. A representative engine map is presented showing the predicted range of efficient operation. After discussion of the engine map, a number of engine features are analyzed individually. These features are: heat transfer and the influence insulating materials have on engine performance and exhaust energy; intake manifold pressure oscillations and interactions with the combustion chamber; and performance losses and seal friction. Finally, code running times and convergence data are presented.

Technology Implementation Plan: Irradiation Testing and Qualification for Nuclear Thermal Propulsion Fuel

Energy Technology Data Exchange (ETDEWEB)

Harrison, Thomas J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Howard, Richard H. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Rader, Jordan D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2017-09-01

This document is a notional technology implementation plan (TIP) for the development, testing, and qualification of a prototypic fuel element to support design and construction of a nuclear thermal propulsion (NTP) engine, specifically its pre-flight ground test. This TIP outlines a generic methodology for the progression from non-nuclear out-of-pile (OOP) testing through nuclear in-pile (IP) testing, at operational temperatures, flows, and specific powers, of an NTP fuel element in an existing test reactor. Subsequent post-irradiation examination (PIE) will occur in existing radiological facilities. Further, the methodology is intended to be nonspecific with respect to fuel types and irradiation or examination facilities. The goals of OOP and IP testing are to provide confidence in the operational performance of fuel system concepts and provide data to program leadership for system optimization and fuel down-selection. The test methodology, parameters, collected data, and analytical results from OOP, IP, and PIE will be documented for reference by the NTP operator and the appropriate regulatory and oversight authorities. Final full-scale integrated testing would be performed separately by the reactor operator as part of the preflight ground test.

Qualification of a Method to Calculate the Irrecoverable Pressure Loss in High Reynolds Number Piping Systems

Energy Technology Data Exchange (ETDEWEB)

Sigg, K. C.; Coffield, R. D.

2002-09-01

High Reynolds number test data has recently been reported for both single and multiple piping elbow design configurations at earlier ASME Fluid Engineering Division conferences. The data of these studies ranged up to a Reynolds number of 42 x 10[sup]6 which is significantly greater than that used to establish design correlations before the data was available. Many of the accepted design correlations, based on the lower Reynolds number data, date back as much as fifty years. The new data shows that these earlier correlations are extremely conservative for high Reynolds number applications. Based on the recent high Reynolds number information a new recommended method has been developed for calculating irrecoverable pressure loses in piping systems for design considerations such as establishing pump sizing requirements. This paper describes the recommended design approach and additional testing that has been performed as part of the qualification of the method. This qualification testing determined the irrecoverable pressure loss of a piping configuration that would typify a limiting piping section in a complicated piping network, i.e., multiple, tightly coupled, out-of-plane elbows in series under high Reynolds number flow conditions. The overall pressure loss measurements were then compared to predictions, which used the new methodology to assure that conservative estimates for the pressure loss (of the type used for pump sizing) were obtained. The recommended design methodology, the qualification testing and the comparison between the predictions and the test data are presented. A major conclusion of this study is that the recommended method for calculating irrecoverable pressure loss in piping systems is conservative yet significantly lower than predicted by early design correlations that were based on the extrapolation of low Reynolds number test data.

Europeans come together on qualification

International Nuclear Information System (INIS)

Whittle, J.

1996-01-01

Utilities operating nuclear power plants in Europe have formed the European Network for Inspection Qualification (ENIQ) to produce a common approach to demonstrating that non-destructive testing is capable providing the information to ensure the absence of significant defects in nuclear plants. Major developments over recent months have included the issue by ENIQ of a formal document defining the methodology for the conduct of qualification which sets out the principles that detailed systems, within an individual country context, should embody. A pilot study on pipe welds typical of those in BWR recirculation loops is being conducted to explore the issues involved in the practical application of the methodology. In parallel with ENIQ, the European Nuclear Regulators Working Group has set up a Task Force in an attempt to define a common regulatory position on non-destructive testing qualifications and has produced its own document which is wider in scope than that of ENIQ. (UK)

Systems engineering approach towards performance monitoring of emergency diesel generator

International Nuclear Information System (INIS)

Nurhayati Ramli; Lee, Y.K.

2013-01-01

Full-text: Systems engineering is an interdisciplinary approach and means to enable the realization of successful systems. In this study, systems engineering approach towards the performance monitoring of Emergency Diesel Generator (EDG) is presented. Performance monitoring is part and parcel of predictive maintenance where the systems and components conditions can be detected before they result into failures. In an effort to identify the proposal for addressing performance monitoring, the EDG boundary has been defined. Based on the Probabilistic Safety Analysis (PSA) results and industry operating experiences, the most critical component is identified. This paper proposed a systems engineering concept development framework towards EDG performance monitoring. The expected output of this study is that the EDG reliability can be improved by the performance monitoring alternatives through the systems engineering concept development effort. (author)

Mechanical Engineering at RWTH Aachen University: Professional Curriculum Development and Teacher Training

Science.gov (United States)

Henning, Klaus; Bornefeld, Gero; Brall, Stefan

2007-01-01

This paper offers a multi-perspective view on engineering education at RWTH Aachen University: curriculum design, examples of newly developed teaching methods for engineering curricula, and teaching competencies and teacher qualification. It is based on the theories of student-centred learning, project learning, social skills, etc., but the paper…

Interface Engineering and Gate Dielectric Engineering for High Performance Ge MOSFETs

Directory of Open Access Journals (Sweden)

Jiabao Sun

2015-01-01

Full Text Available In recent years, germanium has attracted intensive interests for its promising applications in the microelectronics industry. However, to achieve high performance Ge channel devices, several critical issues still have to be addressed. Amongst them, a high quality gate stack, that is, a low defect interface layer and a dielectric layer, is of crucial importance. In this work, we first review the existing methods of interface engineering and gate dielectric engineering and then in more detail we discuss and compare three promising approaches (i.e., plasma postoxidation, high pressure oxidation, and ozone postoxidation. It has been confirmed that these approaches all can significantly improve the overall performance of the metal-oxide-semiconductor field effect transistor (MOSFET device.

Strategy for Qualification of the Plutonium Immobilized Form

International Nuclear Information System (INIS)

Marra, J.C.; Marra, S.L.; Bibler, N.E.; Strachan, D.M.; Shaw, H.F.

1998-01-01

In order to dispose of a radioactive waste form in a federal high- level waste repository, a waste form qualification strategy and program must be developed. The waste form qualification program must include the acceptance specifications for the product, show how compliance with these specifications will be met, and then demonstrate compliance. An important element of this program is developing a measure to demonstrate product consistency. For the can- in-canister option, waste form qualification is needed not only for the Pu immobilized form but also for the high-level waste glass canister containing the Pu waste form. The latter will require close interaction and coordination with the U.S. Department of Energy - Office of Environmental Management (DOE-EM) who, through their contractor at the Savannah River Site (SRS), is the producer of the high-level waste form at the Defense Waste Processing Facility (DWPF). In this paper a waste form qualification strategy for the plutonium ceramic form is described that utilizes, as much as possible, the qualification strategy successfully used for vitrified high-level waste

Qualification of UT methods and systems used for in-service inspections of VVER 440 vessels

International Nuclear Information System (INIS)

Skala, Z.; Vit, J.

2003-01-01

SKODA JS has been performing automated in-service inspections VVER reactor pressure vessels for more than twenty years. All of these inspections were performed by ultrasonic pulse echo method, combined from 1996 with eddy current testing. The Time of Flight Diffraction Method (TOFD) is one of modern methods of ultrasonic testing. The accuracy of sizing the through wall extent of a flaw by TOFD is much better than the accuracy achievable by the pulse echo method. A series of laboratory tests were performed by SKODA JS and confirmed the suitability of TOFD method for VVER reactor parts testing. The Czech Atomic law demands the qualification of systems and methods used for the in-service inspections of nuclear reactors. The qualification is done in accordance with ENIQ methodology and consists of preparation of the Technical Justification and practical tests made under the surveillance of Qualification Body. SKODA JS intends to qualify systems and methods used for the automated ultrasonic testing of VVER 440 and VVER 1000 reactor components from the inner as well as from the outer surface. The accuracy of the flaw through wall extent sizing by TOFD was confirmed by the qualification of methods and systems used for the testing of VVER 440 vessel circumferential weld and so the TOFD method shall be used routinely by SKODA JS for the inspection of vessel circumferential welds root area and for sizing of flaws exceeding the acceptance level. (author)

49 CFR 214.349 - Training and qualification of watchmen/lookouts.

Science.gov (United States)

2010-10-01

... 49 Transportation 4 2010-10-01 2010-10-01 false Training and qualification of watchmen/lookouts...) FEDERAL RAILROAD ADMINISTRATION, DEPARTMENT OF TRANSPORTATION RAILROAD WORKPLACE SAFETY Roadway Worker Protection § 214.349 Training and qualification of watchmen/lookouts. (a) The training and qualification for...

SRS H1616 Hydride Transport Vessel Qualification Report

International Nuclear Information System (INIS)

Smith, A.C.

1999-01-01

This report serves as the design qualification basis for both transport and facility use. Headings identify report sections as containing qualification information for transport use, facility use, or both transport and facility use

SRS H1616 Hydride Transport Vessel Qualification Report

International Nuclear Information System (INIS)

Van Alstine, M.N.

1998-01-01

This report serves as the design qualification basis for both transport and facility use. Headings identify report sections as containing qualification information for transport use, facility use, or both transport and facility use

Affordable Development and Qualification Strategy for Nuclear Thermal Propulsion

Science.gov (United States)

Gerrish, Harold P., Jr.; Doughty, Glen E.; Bhattacharyya, Samit K.

2013-01-01

Nuclear Thermal Propulsion (NTP) is a concept which uses a nuclear reactor to heat a propellant to high temperatures without combustion and can achieve significantly greater specific impulse than chemical engines. NTP has been considered many times for human and cargo missions beyond low earth orbit. A lot of development and technical maturation of NTP components took place during the Rover/NERVA program of the 60's and early 70's. Other NTP programs and studies followed attempting to further mature the NTP concept and identify a champion customer willing to devote the funds and support the development schedule to a demonstration mission. Budgetary constraints require the use of an affordable development and qualification strategy that takes into account all the previous work performed on NTP to construct an existing database, and include lessons learned and past guidelines followed. Current guidelines and standards NASA uses for human rating chemical rocket engines is referenced. The long lead items for NTP development involve the fuel elements of the reactor and ground testing the engine system, subsystem, and components. Other considerations which greatly impact the development plans includes the National Space Policy, National Environmental Policy Act, Presidential Directive/National Security Council Memorandum #25 (Scientific or Technological Experiments with Possible Large-Scale Adverse Environmental Effects and Launch of Nuclear Systems into Space), and Safeguards and Security. Ground testing will utilize non-nuclear test capabilities to help down select components and subsystems before testing in a nuclear environment to save time and cost. Existing test facilities with minor modifications will be considered to the maximum extent practical. New facilities will be designed to meet minimum requirements. Engine and test facility requirements are based on the driving mission requirements with added factors of safety for better assurance and reliability

Integrated Information System for Higher Education Qualifications

Directory of Open Access Journals (Sweden)

Catalin Ionut SILVESTRU

2012-10-01

Full Text Available In the present article we aim to study thoroughly and detail aspects related to architectures specific for e-learning and management of human resources training interconnected to management of qualifications. In addition, we take into consideration combining e-learning architectures with software in an e-learning system interconnected with the National Registry of Qualifications of Higher Education, in view of developing and information system that correlates educational supply from higher education from Romania with labor market demands through qualifications. The scientific endeavor consists of original architectural solutions to integrate data, systems, processes, services from various sources and to use them in the proposed system. The practical result of the scientific endeavor is represented by design of architectures required for developing an e-learning system interconnected with the National Registry of Qualifications from Romania, which involve in first stage the qualifications provided by higher education. The proposed innovative solution consists in the fact that the proposed information system combines the advantages of content management system (CMS with learning content management system (LCMS and with reusable learning objects (RLO. Thus, the architecture proposed in the research ensures the integration of a content management system with a portal for information, guidance and support in making a professional project. The integration enables correlation of competences with content areas and specific items from various teaching subjects, thus evaluating the usefulness for this registry from learning/educational perspective. Using the proposed information system in enables correlation among qualifications, content of educational program and continuous self-evaluation opportunities, which facilitate monitoring of progress and adjustment of learning content.

Chapter 9. Personnel qualification and training

International Nuclear Information System (INIS)

2001-01-01

the direct supervision of the trainer within 4 to 10 weeks after the successful completion of both written and oral of examination. Last year the committee held thirteen sessions for oral theoretical examination. The number of licenses issued in 2000 and the total number of valid licenses is given in table. The standard of professional skills of the staff at nuclear installations is a very important factor for assuring and maintaining a high level of nuclear safety of nuclear installations. Conclusions from inspections and tests as well as results from operation and start up of nuclear units confirm that in this area a high standard of operational safety is being achieved on a permanent basis. Increasing the qualification of UJD staff was done in a form of training and courses scheduled in the plan of training for UJD staff for 2000. These training, composed of specialised qualification study, functional study, as well as study aimed at maintaining qualification. Training courses organised by the Government Office of Slovakia and the IAEA were also of a significant benefit and UJD staff participated on foreign training courses, seminars and conferences, focusing on maintaining and improvement of professional skills. In January 2000 the agreement on co-operation with the Faculty of Natural Science of Comenius University in Bratislava and UJD on INIS system performance (INIS Slovak National Center) was signed

Developing competence based qualification system in the nuclear energy sector

International Nuclear Information System (INIS)

Ceclan, Mihail

2016-01-01

The Institute for Energy and Transport of the Joint Research Centre, European Commission, developed a strategy and road map for ECVET implementation. The JRC road map for European Credit System for Vocational Education and Training (ECVET) implementation has reached the stage of Competence-Based Qualification System development. The Competence-Based Qualification System can help bridge the gap between Human Resources demand and supply in the nuclear market by structuring qualifications in small independent parts. This very specific ECVET feature of a qualification, facilitates the process of competences accumulation and the lifelong learning, mobility and flexible learning pathways. New developments are presented about the Competence-Based Qualification System development for the nuclear energy sector.

Developing competence based qualification system in the nuclear energy sector

Energy Technology Data Exchange (ETDEWEB)

Ceclan, Mihail [European Commission, Petten (Netherlands). Inst. for Energy and Transport

2016-04-15

The Institute for Energy and Transport of the Joint Research Centre, European Commission, developed a strategy and road map for ECVET implementation. The JRC road map for European Credit System for Vocational Education and Training (ECVET) implementation has reached the stage of Competence-Based Qualification System development. The Competence-Based Qualification System can help bridge the gap between Human Resources demand and supply in the nuclear market by structuring qualifications in small independent parts. This very specific ECVET feature of a qualification, facilitates the process of competences accumulation and the lifelong learning, mobility and flexible learning pathways. New developments are presented about the Competence-Based Qualification System development for the nuclear energy sector.

Environmental data qualification system

International Nuclear Information System (INIS)

Hester, O.V.; Groh, M.R.

1989-01-01

The Integrated Environmental Data Management System (IEDMS) is a PC-based system that can support environmental investigations from their design stage and throughout the duration of the study. The system integrates data originating from the Sampling and Analysis Plan, field data and analytical findings. The IEDMS automated features include sampling guidance forms, barcoded sample labels and tags, field and analytical forms reproduction, sample tracking, analytical data qualification, completeness reports, and results and QC data reporting. The IEDMS has extensive automated capabilities that support a systematic and comprehensive process for performing quality assessment of EPA-CLP chemical analyses data. One product of this process is a unique and extremely useful tabular presentation of the data. One table contains the complete set of results and QC data included on the CLP data forms while presenting the information consistent with the chronology in which the analysis was performed. 3 refs., 1 fig

A Strategic Approach for Supporting the Future of Civil Engineering Education in Europe

Science.gov (United States)

Angelides, Demos C.; Loukogeorgaki, Eva

2005-01-01

A new strategic vision of the extensively debated European higher education is proposed with focus on civil engineering. Civil engineering education for the future is considered with relevance to potential world-wide trends and anticipated societal requirements and, therefore, required employee qualifications of the construction-related providers…

Commissioning and Performance Analysis of WhisperGen Stirling Engine

Science.gov (United States)

Pradip, Prashant Kaliram

Stirling engine based cogeneration systems have potential to reduce energy consumption and greenhouse gas emission, due to their high cogeneration efficiency and emission control due to steady external combustion. To date, most studies on this unit have focused on performance based on both experimentation and computer models, and lack experimental data for diversified operating ranges. This thesis starts with the commissioning of a WhisperGen Stirling engine with components and instrumentation to evaluate power and thermal performance of the system. Next, a parametric study on primary engine variables, including air, diesel, and coolant flowrate and temperature were carried out to further understand their effect on engine power and efficiency. Then, this trend was validated with the thermodynamic model developed for the energy analysis of a Stirling cycle. Finally, the energy balance of the Stirling engine was compared without and with heat recovery from the engine block and the combustion chamber exhaust.

On tungsten technologies and qualification for DEMO

International Nuclear Information System (INIS)

Laan, J. van der; Hegeman, H.; Wouters, O.; Luzginova, N.; Jonker, B.; Van der Marck, S.; Opschoor, J.; Wang, J.; Dowling, G.; Stuivenga, M.; Carton, E.

2009-01-01

Tungsten alloys are considered prime candidates for the in-vessel components directly facing the plasma. For example, in the HEMJ helium cooled divertor design tiles may be operated at temperatures up to 1700 deg. C, supported by a structure partially consisting of tungsten at temperatures from 600 to 1000 deg. C, and connected to a HT steel structure. The tungsten armoured primary wall is operated at 500-900 deg. C. Irradiation doses will be few tens dpa at minimum, but FPR requirements for plants availability will stretch these targets. Recently injection moulding technology was developed for pure tungsten and representative parts were manufactured for ITER monobloc divertors and DEMO HEMJ thimbles. The major advantages for this technology are the efficient use of material feedstock/resources and the intrinsic possibility to produce near-finished product, avoiding machining processes that are costly and may introduce surface defects deteriorating the component in service performance. It is well suited for mass-manufacturing of components as well known in e.g. lighting industries. To further qualify this material technology various specimen types were produced with processing parameters identical to the components, and tested successfully, showing the high potential for implementation in (fusion) devices. Furthermore, the engineering approach can clearly be tailored away from conventional design and manufacturing technologies based on bulk materials. The technology is suitable for shaping of new W-alloys and W-ODS variants as well. Basically this technology allows a particular qualification trajectory. There is no need to produce large batches of material during the material development and optimization stage. For the verification of irradiation behaviour in the specific neutron spectra, there is a further attractive feature to use e.g. isotope tailored powders to adjust to available irradiation facilities like MTR's. In addition the ingrowth of transmutation

IEEE Std 600: IEEE trial-use standard requirements for organizations that conduct qualification testing of safety systems equipment for use in nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1992-01-01

The purpose of this standard is to provide requirements for establishing a program for conducting qualification tests of safety systems equipment used in nuclear power generating stations. Compliance with the requirements of this standard does not assure the adequacy of the qualification tests performed. This standard applies to organizations that conduct qualification tests on equipment that has a definable safety function and is an identifiable part of a safety system for use in nuclear power generating stations. It requires a technical program, a quality assurance program, and a demonstrated ability to meet specified technical requirements. It does not apply to materials tests, production tests, normal performance testing, qualification by analysis, qualification by operating experience, or reliability tests such as diesel-generator multiple start tests. The intent of this standard is to achieve greater consistency, reliability, and reproducibility of test results and to provide adequate control of qualification testing of safety systems equipment

NVESTIGATION OF INTERNATIONAL ENGINEERING LICENSURE SYSTEMS

Directory of Open Access Journals (Sweden)

Selim BARADAN

2009-01-01

Full Text Available In many countries, engineers are legally required to register to a "licensure" system, which is founded on education and experience criteria and administered by a government body, to use the "engineer" title and offer professional services to the public. In today's globalized world, international alliances such as FEANI, APEC and EMF award engineers with European, APEC and International Professional engineer titles within a framework of mutual recognition of qualifications enabling them to practice outside their own country. This article examines such international licensure systems, particularly their administration processes and registration criteria, and discusses how current licensure procedures in Turkey should be revamped in case of joining an international alliance such as European Union.

Thermal Analysis for Environmental Qualification of Kori Nuclear power plant unit 3 and 4

International Nuclear Information System (INIS)

Seo, Kwi Hyun; Byun, Choong Sup; Song, Dong Soo

2006-01-01

This paper shows the temperature profiles of safety related electrical equipment exposed to MSLB inside containment. It must be demonstrated that the LOCA qualification conditions exceed or are equivalent to the maximum calculated MSLB conditions. COPATTA as Bechtel's vendor code is used for the containment pressure and temperature prediction in power uprating project for Kori 3,4 and Yonggwang 1,2 nuclear power plants(NPPs). However, CONTEMPT-LT/028 is used for calculating the containment pressure and temperatures in equipment qualification project for the same NPPs. Power uprating code that is, COPATTA benchmarking study performed in six equipment at saturation temperature and surface temperature. Specially, thermal analysis carefully investigate that view point environmental qualification and NUREG- 0588 be mentioned in regard to safety-related heat sink it boundary condition or geometry information

Thermal Analysis for Environmental Qualification of Kori Nuclear power plant unit 3 and 4

Energy Technology Data Exchange (ETDEWEB)

Seo, Kwi Hyun [ENERGEO Inc., Sungnam (Korea, Republic of); Byun, Choong Sup; Song, Dong Soo [KEPRI, Taejon (Korea, Republic of)

2006-07-01

This paper shows the temperature profiles of safety related electrical equipment exposed to MSLB inside containment. It must be demonstrated that the LOCA qualification conditions exceed or are equivalent to the maximum calculated MSLB conditions. COPATTA as Bechtel's vendor code is used for the containment pressure and temperature prediction in power uprating project for Kori 3,4 and Yonggwang 1,2 nuclear power plants(NPPs). However, CONTEMPT-LT/028 is used for calculating the containment pressure and temperatures in equipment qualification project for the same NPPs. Power uprating code that is, COPATTA benchmarking study performed in six equipment at saturation temperature and surface temperature. Specially, thermal analysis carefully investigate that view point environmental qualification and NUREG- 0588 be mentioned in regard to safety-related heat sink it boundary condition or geometry information.

Performance and Qualification of the Power Supply and Control Unit for the HEMP Thruster

Science.gov (United States)

Brag, R.; Herty, F.

2014-08-01

In 2013, Astrium GmbH delivered several flight model electronics for Electric Propulsion (EP) systems or corresponding components. One of the elements is a Power Supply and Control Unit (PSCU) for the Thales development "High Efficiency Multistage Plasma Thruster" (HEMP-T) (see Figure 1). This paper presents the PSCU specification and results of the qualification and acceptance phase of the EQM and the PFM.

10 CFR 50.76 - Licensee's change of status; financial qualifications.

Science.gov (United States)

2010-01-01

... the financial qualifications information that would be required for obtaining an initial operating license as specified in § 50.33(f)(2). The financial qualifications information must address the first... 10 Energy 1 2010-01-01 2010-01-01 false Licensee's change of status; financial qualifications. 50...

Performance simulation of a spark ignited free-piston engine generator

Energy Technology Data Exchange (ETDEWEB)

Mikalsen, R.; Roskilly, A.P. [Sir Joseph Swan Institute for Energy Research, University of Newcastle upon Tyne, Newcastle upon Tyne, NE1 7RU (United Kingdom)

2008-10-15

Free-piston engines are under investigation by a number of research groups worldwide due to potential fuel efficiency and engine emissions advantages. The free-piston engine generator, in which a linear electric generator is fixed to the mover to produce electric power, has been proposed as an alternative prime mover for hybrid-electric vehicles. This paper investigates the performance of a spark ignited free-piston engine generator and compares it to a conventional engine using a computational fluid dynamics simulation model. The particular operating characteristics of the free-piston engine were not found to give noticeable performance advantages, and it is concluded that the main potential of this technology lies in the simplicity and flexibility of the concept. (author)

Test report: Electron-proton spectrometer qualification test unit, qualification test

Science.gov (United States)

Vincent, D. L.

1972-01-01

Qualification tests of the electron-proton spectrometer test unit are presented. The tests conducted were: (1) functional, (2) thermal/vacuum, (3) electromagnetic interference, (4) acoustic, (5) shock, (6) vibration, and (7) humidity. Results of each type of test are presented in the form of data sheets.

Qualification testing and electrical measurement experience: A manufacturer's view

Science.gov (United States)

Arnett, J. C.; Cooley, J. E.; Wingert, T. L.

1983-11-01

ARCO Solar's experiences as a participant in an industry-utility-government environmental qualification team examining photovoltaic devices are discussed. Included is an assessment of the applicability, completeness and appropriateness of the testing procedures and of the acceptance criteria for megawatt-sized procurements for utilities. Like the stand-alone users, the utility industry is interested in obtaining low costs, but additional concerns exist related to reliability and durability, safety, grounding and overall system criteria including performance prediction (related to output power acceptance testing), power quality and dispatchability. For purposes of this first major purchase of photovoltaic modules and panels by the utility industry, there was a carry-over of the JPL specifications. The need exists for futher development, assessement, and selection of qualification and testing standards and evaluation criteria specifically addressing these additional concerns for utility-connected PV power-plant applications.

[Additional qualification in health economics--a pre-condition for ENT leadership positions?].

Science.gov (United States)

Lehnerdt, G; Schöffski, O; Mattheis, S; Hoffmann, T K; Lang, S

2013-11-01

The increasing medical-technical progress as well as the dramatic demographic changes cause problems with regard to rapid enlargement of medical service offers, allocation of resources and a financing shortfall in the German public health system. The economization in the German Health System can also be perceived in ENT departments. After performing an internet search about the rapidly growing market for qualifications measures in health economics, we hence conducted an anonymous survey for ENT senior doctors and directors of the 34 German University Departments to evaluate their attitude towards, as well as their expectation of such an add-on qualification. Since the German government finalized the health care reform in the year 2000 such qualification measures rapidly developed: amongst others, 26 postgraduate, extra-occupational master programs have been inaugurated. The anonymous survey was answered by 105 ENT doctors (63 senior doctors, 27 vice professors and 15 directors). 63% out of these 105 colleagues considered such an add-on qualification to be mandatory. 41% of the colleagues were already "add-on qualified" in that field, only 10 of them by means of a study program. 71 of 105 colleagues (68%) considered the add-on qualification to be advantageous for their future personal career. With regard to the designated contents of the study program, "Staff Management" was even prioritized to "Hospital Financing" and "Cost Accounting". Aspects of management and a (health-) economical basic knowledge became an integral part of the daily routine for "first-line management doctors" also in (University) ENT-departments. © Georg Thieme Verlag KG Stuttgart · New York.

Evaluation of environmental qualification period for Conax electrical penetration assemblies. Final report

International Nuclear Information System (INIS)

Doroshuk, B.; Hager, M.; Brown, R.

1995-05-01

This report evaluates the environmental qualification period of Conax electrical penetration assemblies (EPAs) for extension from forty (40) years to sixty (60) years. The evaluation was performed based on a review of Conax EPAs supplied to Baltimore Gas ampersand Electric's (BGE) Calvert Cliffs Nuclear Power Plant Units 1 and 2. The report has been prepared so that it may be of use to any utility involved in the extension of the environmental qualification period for Conax EPAs installed in their plant(s). The report includes a section on the strategy which was developed for the effort to extend the qualified lives of the Conax EPAs. A review of documentation and plant conditions specific to BGE is included in the report to demonstrate the methodology. The documentation included qualification testing performed by Conax of the materials of construction of the EPA models. The plant conditions reviewed included both normal and accident environments, both of which are specific to Calvert Cliffs Nuclear Power Plant Units 1 and 2. This report can be used as a guide in the evaluation of similar installations of Conax electrical penetration assemblies in other nuclear power plants by applying the methodologies used herein in conjunction with the plant specific test reports, materials, and conditions

Program plan for environmental qualification of mechanical and dynamic (including seismic) qualification of mechanical and electrical equipment program (EDQP)

International Nuclear Information System (INIS)

Weidenhamer, G.H.

1986-06-01

The equipment qualification program described in this plan is intended to provide the technical basis for resolving uncertainties in existing equipment qualification standards. In addition, research results are contributing to the resolution of safety issues GI-23, GI-87, USI-A44, titled, ''Reactor Coolant Pump Seal Failure,'' ''Failure of HPCI Steam Line Without Isolation,'' and ''Station Blackout,'' respectively. Also, research effort is being directed at providing information on the behavior of containment isolation valves under severe accident environments. Although the results of the latter research will not contribute to resolving uncertainties in qualification standards, it has proven cost effective to obtain this information under this program

Code qualification of structural materials for AFCI advanced recycling reactors.

Energy Technology Data Exchange (ETDEWEB)

Natesan, K.; Li, M.; Majumdar, S.; Nanstad, R.K.; Sham, T.-L. (Nuclear Engineering Division); (ORNL)

2012-05-31

This report summarizes the further findings from the assessments of current status and future needs in code qualification and licensing of reference structural materials and new advanced alloys for advanced recycling reactors (ARRs) in support of Advanced Fuel Cycle Initiative (AFCI). The work is a combined effort between Argonne National Laboratory (ANL) and Oak Ridge National Laboratory (ORNL) with ANL as the technical lead, as part of Advanced Structural Materials Program for AFCI Reactor Campaign. The report is the second deliverable in FY08 (M505011401) under the work package 'Advanced Materials Code Qualification'. The overall objective of the Advanced Materials Code Qualification project is to evaluate key requirements for the ASME Code qualification and the Nuclear Regulatory Commission (NRC) approval of structural materials in support of the design and licensing of the ARR. Advanced materials are a critical element in the development of sodium reactor technologies. Enhanced materials performance not only improves safety margins and provides design flexibility, but also is essential for the economics of future advanced sodium reactors. Code qualification and licensing of advanced materials are prominent needs for developing and implementing advanced sodium reactor technologies. Nuclear structural component design in the U.S. must comply with the ASME Boiler and Pressure Vessel Code Section III (Rules for Construction of Nuclear Facility Components) and the NRC grants the operational license. As the ARR will operate at higher temperatures than the current light water reactors (LWRs), the design of elevated-temperature components must comply with ASME Subsection NH (Class 1 Components in Elevated Temperature Service). However, the NRC has not approved the use of Subsection NH for reactor components, and this puts additional burdens on materials qualification of the ARR. In the past licensing review for the Clinch River Breeder Reactor Project (CRBRP

Performance of Diesel Engine Using Blended Crude Jatropha Oil

Science.gov (United States)

Kamarudin, Kamarul Azhar; Mohd Sazali, Nor Shahida Akma; Mohd Ali, Mas Fauzi; Alimin, Ahmad Jais; Khir, Saffiah Abdullah

2010-06-01

Vegetable oil presents a very promising alternative to diesel oil since it is renewable and has similar properties to the diesel. In view of this, crude jatropha oil is selected and its viscosity is reduced by blending it with diesel. Since jatropha oil has properties which are similar to mineral diesel, it can be used in compression ignition engines without any engine modification. This paper presents the results of investigation carried out on a four-cylinder, four strokes and indirect-injection diesel engine. The engine, operated using composition blends of crude jatropha oil and diesel, were compared with mineral diesel. An experimental investigation has been carried out to analyze the performance characteristics of a compression ignition engine from the blended fuel (5%, 10%, 20% and 30%). A naturally aspirated four-stroke indirect injection diesel engine was tested at full load conditions, speeds between 1000 and 3500 rpm with intervals of 500 rpm. Results obtained from the measures of torque, power, specific fuel consumptions, thermal efficiency and brake mean effective pressure are nearly the same between blended and diesel fuel. An overall graph shows that the performance of relevant parameters from blended fuel is most likely similar to the performance produced from diesel. The experimental results proved that the use of crude jatropha oil in compression ignition engines is a viable alternative to diesel.

Design and Implementation of High-Performance GIS Dynamic Objects Rendering Engine

Science.gov (United States)

Zhong, Y.; Wang, S.; Li, R.; Yun, W.; Song, G.

2017-12-01

Spatio-temporal dynamic visualization is more vivid than static visualization. It important to use dynamic visualization techniques to reveal the variation process and trend vividly and comprehensively for the geographical phenomenon. To deal with challenges caused by dynamic visualization of both 2D and 3D spatial dynamic targets, especially for different spatial data types require high-performance GIS dynamic objects rendering engine. The main approach for improving the rendering engine with vast dynamic targets relies on key technologies of high-performance GIS, including memory computing, parallel computing, GPU computing and high-performance algorisms. In this study, high-performance GIS dynamic objects rendering engine is designed and implemented for solving the problem based on hybrid accelerative techniques. The high-performance GIS rendering engine contains GPU computing, OpenGL technology, and high-performance algorism with the advantage of 64-bit memory computing. It processes 2D, 3D dynamic target data efficiently and runs smoothly with vast dynamic target data. The prototype system of high-performance GIS dynamic objects rendering engine is developed based SuperMap GIS iObjects. The experiments are designed for large-scale spatial data visualization, the results showed that the high-performance GIS dynamic objects rendering engine have the advantage of high performance. Rendering two-dimensional and three-dimensional dynamic objects achieve 20 times faster on GPU than on CPU.

Airbreathing Pulse Detonation Engine Performance

Science.gov (United States)

Povinelli, Louis A.; Yungster, Shaye

2002-01-01

This paper presents performance results for pulse detonation engines (PDE) taking into account the effects of dissociation and recombination. The amount of sensible heat recovered through recombination in the PDE chamber and exhaust process was found to be significant. These results have an impact on the specific thrust, impulse and fuel consumption of the PDE.

Similarity principles for seismic qualification of equipment by experience data

International Nuclear Information System (INIS)

Kana, D.D.; Pomerening, D.J.

1989-01-01

A methodology is developed for seismic qualification of nuclear plant equipment by applying similarity principles to existing experience data. Experience data is that available from previous qualifications by analysis or testing, or from actual earthquake events. Similarity principles are defined in terms of excitation, equipment physical characteristics, and equipment response. Physical similarity is further defined in terms of a critical transfer function for response at a location on a primary structure, whose response can be assumed directly related to fragility of the item under elevated levels of excitation. Procedures are developed for combining experience data into composite specifications for qualification of equipment that can be shown to be physically similar to the reference equipment. Other procedures are developed for extending qualifications beyond the original specifications under certain conditions. Some examples for application and verification of the procedures are given for actual test data available from previous qualifications. The developments are intended to elaborate on the rather broad guidelines by the IEEE 344 Standards Committee for equipment qualification in new nuclear plants. The results also contribute to filling a gap that exists between the IEEE 344 methodology and that which was previously developed for equipment in existing plants by the Seismic Qualification Utilities Group. 10 refs., 9 figs., 1 tab

Surface engineering for enhanced performance against wear

CERN Document Server

2013-01-01

Surface Engineering constitutes a variety of processes and sub processes. Each chapter of this work covers specific processes by experts working in the area. Included for each topic are tribological performances for each process as well as results of recent research. The reader also will benefit from in-depth studies of diffusion coatings, nanocomposite films for wear resistance, surfaces for biotribological applications, thin-film wear, tribology of thermal sprayed coatings, hardfacing, plating for tribology and high energy beam surface modifications. Material scientists as well as engineers working with surface engineering for tribology will be particularly interested in this work.

THE EFFECT OF COMPRESSION RATIO VARIATIONS ON THE ENGINE PERFORMANCE PARAMETRES IN SPARK IGNITION ENGINES

Directory of Open Access Journals (Sweden)

Yakup SEKMEN

2005-01-01

Full Text Available Performance of the spark ignition engines may be increased by changing the geometrical compression ratio according to the amount of charging in cylinders. The designed geometrical compression ratio can be realized as an effective compression ratio under the full load and full open throttle conditions since the effective compression ratio changes with the amount of charging into the cylinder in spark ignition engines. So, this condition of the spark ignition engines forces designers to change their geometrical compression ratio according to the amount of charging into the cylinder for improvement of performance and fuel economy. In order to improve the combustion efficiency, fuel economy, power output, exhaust emissions at partial loads, compression ratio must be increased; but, under high load and low speed conditions to prevent probable knock and hard running the compression ratio must be decreased gradually. In this paper, relation of the performance parameters to compression ratio such as power, torque, specific fuel consumption, cylindir pressure, exhaust gas temperature, combustion chamber surface area/volume ratio, thermal efficiency, spark timing etc. in spark ignition engines have been investigated and using of engines with variable compression ratio is suggested to fuel economy and more clear environment.

Engineering and maintenance applied to safety-related valves in nuclear power plants

International Nuclear Information System (INIS)

Verdu, M. F.; Perez-Aranda, J.

2014-01-01

Nuclear Division in Iberdrola engineering and Construction has a team with extensive experience on engineering and services works related to valves. Also, this team is linked to UNESA as Technical support and Reference Center. Iberdrola engineering and construction experience in nuclear power plants valves, gives effective response to engineering and maintenance works that can be demanded in a nuclear power plant and it requires a high degree of qualification and knowledge both in Operation and Outages. (Author)

Guidelines for training and qualification of radiological protection technicians

International Nuclear Information System (INIS)

1987-08-01

These guidelines, used in combination with plant-specific job analysis, provide the framework for a training and qualification program for radiological protection technicians at nuclear power plants. Radiological protection technicians are defined as those individuals, both plant and contractor, who will be engaged in the evaluation of radiological conditions in the nuclear plant and the implementation of the necessary radiological safety measures as they apply to nuclear plant workers and members of the general public. An important aspect of this work is recognizing and handling unusual situations involving radioactivity, including incidents related to degraded core conditions. These guidelines incorporate the results of an industry-wide job analysis and task analysis (JTA) combined with industry operating experience review. However, the industry-wide analyses did not identify all important academic and fundamental knowledge and skills. Further in-depth analysis by subject matter experts produced additional knowledge and skills that were added to these guidelines. All utilities should use these guidelines in conjunction with plant-specific and industry-wide JTA results to develop or validate their radiological protection technician training program. Plant-specific information should be used to establish appropriate training program content. This plant-specific information should reflect unique job duties, equipment, operating experience, and trainee entry-level qualifications. Revisions to these guidelines should be reviewed for applicability and incorporated into the training program using each utility's training system development (TSD) procedures. Plant-specific job analysis and task analysis data is essential to the development of performance-based training programs. These analyses are particularly useful in selecting tasks for training and in developing on-the-job training (OJT), laboratory training, and mock-up training. Qualification programs based on these

Biogas engine performance estimation using ANN

Directory of Open Access Journals (Sweden)

Yusuf Kurtgoz

2017-12-01

Full Text Available Artificial neural network (ANN method was used to estimate the thermal efficiency (TE, brake specific fuel consumption (BSFC and volumetric efficiency (VE values of a biogas engine with spark ignition at different methane (CH4 ratios and engine load values. For this purpose, the biogas used in the biogas engine was produced by the anaerobic fermentation method from bovine manure and different CH4 contents (51%, 57%, 87% were obtained by purification of CO2 and H2S. The data used in the ANN models were obtained experimentally from a 4-stroke four-cylinder, spark ignition engine, at constant speed for different load and CH4 ratios. Using some of the obtained experimental data, ANN models were developed, and the rest was used to test the developed models. In the ANN models, the CH4 ratio of the fuel, engine load, inlet air temperature (Tin, air fuel ratio and the maximum cylinder pressure are chosen as the input parameters. TE, BSFC and VE are used as the output parameters. Root mean square error (RMSE, mean absolute percentage error (MAPE and correlation coefficient (R performance indicators are used to compare measured and predicted values. It has been shown that ANN models give good results in spark ignition biogas engines with high correlation and low error rates for TE, BSFC and VE values.

A comprehensive program of nuclear engineering and science education

International Nuclear Information System (INIS)

Bereznai, G.; Lewis, B.

2014-01-01

The University of Ontario Institute of Technology offers undergraduate degrees in nuclear engineering, nuclear power, health physics and radiation science, graduate degrees (masters as well as doctorate) in nuclear engineering, and graduate diplomas that encompass a wide range of nuclear engineering and technology topics. Professional development programs tailored to specific utility needs are also offered, and the sharing of course material between the professional development and university education courses has strengthened both approaches to ensuring the high qualification levels required of professionals in the nuclear industry. (author)

Qualification Practices in Nuclear Industry: Steam Generator Eddy Current Probe Qualification

International Nuclear Information System (INIS)

Vavrous, M.; Gracin, R.

2010-01-01

Through history of nuclear power plant operation, a large number of nuclear power plant forced outages related to tube failures occurred. It resulted with large amount of repair and outage costs, what initiated implementation of regulated practice of periodical tube examination and tube condition monitoring. Purpose of examinations is to detect existing or potential tube degradations that could affect tube integrity and therefore result in forced outages and unwanted costs related to emergency repair activities and loss of ability for electrical power production. With increased examination activities, additional information about steam generator tube condition became available and additional methods for ensuring tube integrity became available. As the number of examination solutions increased, need for validation and assessment of examination methods occurred. For that purpose, a large number of standards and guidelines with its requirements were implemented in nuclear industry regulatory requirements to ensure that adequately validated examinations are applied. With this purpose, qualification requirements for inspection activities were implemented with other requirements. With progress of technology, progress was also achieved in examination methods and more advanced examination methods and advanced inspection systems were developed. This advancement is accompanied by advancement in regulatory requirements regarding inspection and monitoring of tube integrity and condition. Ultimate goal of implementation of qualification processes and its requirements in all aspects of nuclear industry is to achieve minimal rate of forced outages, which would ensure maximum electrical power production capabilities and maximum optimization of operational costs while maintaining safe operation in accordance with environmental policies. This article will focus on qualification of steam generator eddy current bobbin probe.(author).

Prediction of small spark ignited engine performance using producer gas as fuel

Directory of Open Access Journals (Sweden)

N. Homdoung

2015-03-01

Full Text Available Producer gas from biomass gasification is expected to contribute to greater energy mix in the future. Therefore, effect of producer gas on engine performance is of great interest. Evaluation of engine performances can be hard and costly. Ideally, they may be predicted mathematically. This work was to apply mathematical models in evaluating performance of a small producer gas engine. The engine was a spark ignition, single cylinder unit with a CR of 14:1. Simulation was carried out on full load and varying engine speeds. From simulated results, it was found that the simple mathematical model can predict the performance of the gas engine and gave good agreement with experimental results. The differences were within ±7%.

High Temperature Materials Interim Data Qualification Report FY 2011

International Nuclear Information System (INIS)

Lybeck, Nancy

2011-01-01

Projects for the very high temperature reactor (VHTR) Technology Development Office provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR program has established the Next Generation Nuclear Plant (NGNP) Data Management and Analysis System (NDMAS) to ensure that VHTR data are qualified for use, stored in a readily accessible electronic form, and analyzed to extract useful results. This document focuses on the first NDMAS objective. It describes the High Temperature Materials characterization data stream, the processing of these data within NDMAS, and reports the interim fiscal year (FY) 2011 qualification status of the data. Data qualification activities within NDMAS for specific types of data are determined by the data qualification category assigned by the data generator. The High Temperature Materials data are being collected under the Nuclear Quality Assurance (NQA)-1 guidelines and will be qualified data. For NQA-1 qualified data, the qualification activities include: (1) capture testing to confirm that the data stored within NDMAS are identical to the raw data supplied, (2) accuracy testing to confirm that the data are an accurate representation of the system or object being measured, and (3) documenting that the data were collected under an NQA-1 or equivalent Quality Assurance program. Currently, data from seven test series within the High Temperature Materials data stream have been entered into the NDMAS vault, including tensile tests, creep tests, and cyclic tests. Of the 5,603,682 records currently in the vault, 4,480,444 have been capture passed, and capture testing is in process for the remaining 1,123,238.

49 CFR 391.11 - General qualifications of drivers.

Science.gov (United States)

2010-10-01

... understand highway traffic signs and signals in the English language, to respond to official inquiries, and... QUALIFICATIONS OF DRIVERS AND LONGER COMBINATION VEHICLE (LCV) DRIVER INSTRUCTORS Qualification and... motor vehicle unless he/she is qualified to drive a commercial motor vehicle. Except as provided in...

29 CFR 1926.1076 - Qualifications of dive team.

Science.gov (United States)

2010-07-01

... 29 Labor 8 2010-07-01 2010-07-01 false Qualifications of dive team. 1926.1076 Section 1926.1076 Labor Regulations Relating to Labor (Continued) OCCUPATIONAL SAFETY AND HEALTH ADMINISTRATION... § 1926.1076 Qualifications of dive team. Note: The requirements applicable to construction work under...

Qualification criteria verification for aisi-4340 steel suspension lug

International Nuclear Information System (INIS)

Riaz, M.A.; Alam, M.

2005-01-01

All external loads carried underneath an aircraft are mounted onto it through mechanism generally known as suspension system. The externally mounted attachments like bombs, missiles and fuel tanks etc. experience enormous aerodynamic and inertial forces in the flights. These forces are transferred to the interface point of suspension system, known as 'Suspension Lug'. Thus lugs are considered critical component and have extremely stringent qualification criteria standards used in the aviation industry in USA, Europe, Russia, etc. Different standards prevail in different parts of the world about qualification and testing of these lugs. As Pakistan is entering into aviation industry, therefore there is a need to fulfill the requirements of these standards, to suit Pakistani environment. The suspension lug under study is 2000 Ibs. load class made from AISI-4340 Steel having good mechanical properties as per required standard. The manufacturing processes included forging, machining and vacuum heat treatment. The prototypes of suspension lugs were manufactured in the local industry and subjected to the required mechanical tests such as tensile testing at 5 to 35 degree angles. Impact testing at cryogenic temperatures of -50 to -70 degree C, and breaking load testing were performed. The acceptable results were obtained and mechanical testing for qualification of lugs was finalized and standardized. The options were compared with practical viability, utilization of product and cost effectiveness. (author)

Review of qualifications for fuel assembly fabrication

International Nuclear Information System (INIS)

Slabu, Dan; Zemek, Martin; Hellwig, Christian

2013-01-01

The required quality of nuclear fuel in industrial production can only be assured by applying processes in fabrication and inspection, which are well mastered and have been proven by an appropriate qualification. The present contribution shows the understanding and experiences of Axpo with respect to qualifications in the frame of nuclear fuel manufacturing and reflects some related expectations of the operator. (orig.)

Re-qualification of switchgear equipment following field modification

International Nuclear Information System (INIS)

Tulk, J.D.; El Bestawi, M.A.

1984-01-01

A set of 4.16 kV switchgear was seismically qualified by shaker table test for use in a nuclear power plant. Later, the equipment was modified by the addition of two extra switches and enclosures. This paper describes the methods used to extend the qualification achieved in the original proof test to the new configuration. Qualification of the modified switchgear depended on demonstrating that the intensity of the shaking that would be experienced by equipment mounted in the extended enclosure during a design basis earthquake (DBE) would be no stronger than the shaking that occurred during the original qualification testing. This was accomplished by a combination of analysis and experiment. Natural frequencies and mode-shapes of the original and extended enclosure structures were determined through in-situ modal tests on the equipment. Mathematical models based on the experimental results were then used for dynamic analyses which generated two sets of in-equipment response spectra: one set representing the original qualification test; and one set representing the response of the modified equipment to a hypothetical DBE. Qualification was confirmed by demonstrating that the test-based response spectra for the original configuration exceeded the response spectra developed for the extended structure subjected to DBE level excitation

Valve performance concept move from preventive to condition-oriented maintenance

International Nuclear Information System (INIS)

Zanner, G.; Kradepohl, P.

1996-01-01

As a turnkey supplier of nuclear and fossil power plants, Siemens must pay attention in concentrating, maintaining, and developing the expertise in many areas such as system design, components, materials, quality assurance, and qualification testing within centralized organizations. In the company segment VALVES, Siemens/KWU is staffed with experienced professionals who have serviced the power plant industry for about 25 years. The valve engineers deal with all kinds of valve and actuator-related activities like design ratings, development, qualifications, and ongoing improvements. In this regard, the engineers are involved in nearly all actual problems and suggested solutions through continuing dialogues with utilities, authorities, and vendors of valves and actuators

Valve performance concept move from preventive to condition-oriented maintenance

Energy Technology Data Exchange (ETDEWEB)

Zanner, G.; Kradepohl, P.

1996-12-01

As a turnkey supplier of nuclear and fossil power plants, Siemens must pay attention in concentrating, maintaining, and developing the expertise in many areas such as system design, components, materials, quality assurance, and qualification testing within centralized organizations. In the company segment VALVES, Siemens/KWU is staffed with experienced professionals who have serviced the power plant industry for about 25 years. The valve engineers deal with all kinds of valve and actuator-related activities like design ratings, development, qualifications, and ongoing improvements. In this regard, the engineers are involved in nearly all actual problems and suggested solutions through continuing dialogues with utilities, authorities, and vendors of valves and actuators.

Chemical Engineering Education - Current and Future Trends

DEFF Research Database (Denmark)

Gani, Rafiqul

topics (transport phenomena, separations, reaction engineering, etc.) must remain strong, should the applications that currently emphasize commodity chemicals also include new topics such as sustainability, and product design? In Europe, the European Federation of Chemical Engineering (EFCE) has taken...... has a product focus. With this shift of the chemical industry, what should be the curriculum of the chemical engineering degrees at the BSc- and MSc-levels, and, are the skill set of chemical engineers appropriate for this altered chemical industry? While the basic skill set, defined by the core...... a leading role to define the chemical engineering curriculum. The result has been a set of recommendations for the first (BSc), second (MSc) and third (PhD) cycle chemical engineering education aligned to the Bologna Process. They recommend that students studying towards bachelor and masters qualifications...

DOE handbook: Guide to good practices for the selection, training, and qualification of shift supervisors

International Nuclear Information System (INIS)

1999-04-01

This Department of Energy (DOE) handbook is approved for use by all DOE Components and their contractors. The Handbook incorporates editorial changes to DOE-STD-1061-93, ''Guide to Good Practices for the Selection, Training, and Qualification of shift Supervisors,'' and supersedes DOE-STD-1061-93. Technical content of this Handbook has not changed from the original technical standard. Changes are primarily editorial improvements, redesignation of the standard to a Handbook, and format changes to conform with current Technical Standards Program procedures. This guide, used in conjunction with a facility-specific job analysis, provides a framework for the selection, training, qualification, and professional development of reactor facility and non-reactor nuclear facility shift supervisors. Training and qualification programs based on this guide should provide assurance that shift supervisors perform their jobs safely and competently

DOE handbook: Guide to good practices for the selection, training, and qualification of shift supervisors

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-04-01

This Department of Energy (DOE) handbook is approved for use by all DOE Components and their contractors. The Handbook incorporates editorial changes to DOE-STD-1061-93, ``Guide to Good Practices for the Selection, Training, and Qualification of shift Supervisors,`` and supersedes DOE-STD-1061-93. Technical content of this Handbook has not changed from the original technical standard. Changes are primarily editorial improvements, redesignation of the standard to a Handbook, and format changes to conform with current Technical Standards Program procedures. This guide, used in conjunction with a facility-specific job analysis, provides a framework for the selection, training, qualification, and professional development of reactor facility and non-reactor nuclear facility shift supervisors. Training and qualification programs based on this guide should provide assurance that shift supervisors perform their jobs safely and competently.

Effect of Injector Nozzle Holes on Diesel Engine Performance

OpenAIRE

Semin,; Yusof, Mohd Yuzri Mohd; Arof, Aminuddin Md; Shaharudin, Daneil Tomo; Ismail, Abdul Rahim

2010-01-01

All of the injector nozzle holes have examined and the results are shown that the seven holes nozzle have provided the best burning result for the fuel in-cylinder burned in any different engine speeds and the best burning is in low speed engine. In engine performance effect, all of the nozzles have examined and the five holes nozzle provided the best result in indicted power, indicated torque and ISFC in any different engine speeds.

Windmilling of turbofan engine; calculation of performance characteristics of a turbofan engine under windmilling

OpenAIRE

Ramanathan, A.

2014-01-01

The turbofan is a type of air breathing jet engine that finds wide use in aircraft propulsion. During the normal operation of a turbofan engine installed in aircraft, the combustor is supplied with fuel, flow to the combustor is cut off and the engine runs under so called Windmilling conditions being driven only by the ram pressure ratio by producing drag. In-depth analysis is done to study the performance characteristics at this state.

Engine performance and emissions characteristics of a diesel engine fueled with diesel-biodiesel-bioethanol emulsions

International Nuclear Information System (INIS)

Tan, Yie Hua; Abdullah, Mohammad Omar; Nolasco-Hipolito, Cirilo; Zauzi, Nur Syuhada Ahmad; Abdullah, Georgie Wong

2017-01-01

Highlights: • Different composition of diesel fuel, biodiesel and bioethanol emulsions were examined. • The fuels were tested in a direct injection diesel engine and parameters were evaluated. • Engine power, torque, exhaust gas temperature & fuel consumptions were compared. • Emulsions fuels emitted lower CO and CO_2 than fossil diesel. • Lower NOx emission was observed at medium engine speeds and loads for emulsion fuels. - Abstract: In this research work, the experimental investigation of the effect of diesel-biodiesel-bioethanol emulsion fuels on combustion, performance and emission of a direct injection (DI) diesel engine are reported. Four kind of emulsion fuels were employed: B (diesel-80%, biodiesel-20% by volume), C (diesel-80%, biodiesel-15%, bioethanol-5%), D (diesel-80%, biodiesel-10%, bioethanol-10%) and E (diesel-80%, biodiesel-5%, bioethanol-15%) to compare its’ performance with the conventional diesel, A. These emulsion fuels were prepared by mechanical homogenizer machine with the help of Tween 80 (1% v/v) and Span 80 (0.5% v/v) as surfactants. The emulsion characteristics were determined by optical electron microscope, emulsification stability test, FTIR, and the physiochemical properties of the emulsion fuels which were all done by following ASTM test methods. The prepared emulsion fuels were then tested in diesel engine test bed to obtain engine performance and exhaust emissions. All the engine experiments were conducted with engine speeds varying from 1600 to 2400 rpm. The results showed the heating value and density of the emulsion fuels decrease as the bioethanol content in the blend increases. The total heating value of the diesel-biodiesel-bioethanol fuels were averagely 21% higher than the total heating value of the pure biodiesel and slightly lower (2%) than diesel fuel. The engine power, torque and exhaust gas temperature were reduced when using emulsion fuels. The brake specific fuel consumption (BSFC) for the emulsion fuels

Qualification of diesel generator exhaust carbon steel piping to intermitted elevated temperatures

International Nuclear Information System (INIS)

Ratiu, M.D.; Moisidis, N.T.

1996-01-01

The diesel generator exhaust piping, usually made up of carbon steel piping (e.g., ASME SA-106, SA-53), is subjected to successive short time exposures at elevated temperatures up to 1,000 F (538 C). A typical design of this piping, without consideration for creep-fatigue cumulative damage, is at least incomplete, if not inappropriate. Also, a design for creep-fatigue, usually employed for long-term exposure to elevated temperatures, would be too conservative and will impose replacement of the carbon steel piping with heat-resistant CrMo alloy piping. The existing ASME standard procedures do not explicitly provide acceptance criteria for the design qualification to withstand these intermittent exposures to elevated temperatures. The serviceability qualification proposed is based on the evaluation of equivalent full temperature cycles which are presumed/expected to be experienced by the exhaust piping during the design operating life of the diesel engine. The proposed serviceability analysis consists of: (a) determination of the permissible stress at elevated temperatures, and (b) estimation of creep-fatigue damage for the total expected cycles of elevated temperature exposures following the procedure provided in ASME Code Cases N-253-6 and N-47-28

Open-Source RTOS Space Qualification: An RTEMS Case Study

Science.gov (United States)

Zemerick, Scott

2017-01-01

NASA space-qualification of reusable off-the-shelf real-time operating systems (RTOSs) remains elusive due to several factors notably (1) The diverse nature of RTOSs utilized across NASA, (2) No single NASA space-qualification criteria, lack of verification and validation (V&V) analysis, or test beds, and (3) different RTOS heritages, specifically open-source RTOSs and closed vendor-provided RTOSs. As a leader in simulation test beds, the NASA IV&V Program is poised to help jump-start and lead the space-qualification effort of the open source Real-Time Executive for Multiprocessor Systems (RTEMS) RTOS. RTEMS, as a case-study, can be utilized as an example of how to qualify all RTOSs, particularly the reusable non-commercial (open-source) ones that are gaining usage and popularity across NASA. Qualification will improve the overall safety and mission assurance of RTOSs for NASA-agency wide usage. NASA's involvement in space-qualification of an open-source RTOS such as RTEMS will drive the RTOS industry toward a more qualified and mature open-source RTOS product.

Extraction, -scrub, -strip test results from the interim salt disposition program macrobatch 10 tank 21H qualification samples

Energy Technology Data Exchange (ETDEWEB)

Peters, T. B. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2017-06-26

Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 10 for the Interim Salt Disposition Program (ISDP). The Salt Batch 10 characterization results were previously reported.ii,iii An Extraction, -Scrub, -Strip (ESS) test was performed to determine cesium distribution ratios (D(Cs)) and cesium concentration in the strip effluent (SE) and decontaminated salt solution (DSS) streams; this data will be used by Tank Farm Engineering to project a cesium decontamination factor (DF). This test used actual Tank 21H material, and a sample of the NGS Blend solvent currently being used at the Modular Caustic-Side Solvent Extraction Unit (MCU). The ESS test showed acceptable performance with an extraction D(Cs) value of 110. This value is consistent with results from previous salt batch ESS tests using similar solvent formulations. This is better than the predicted value of 39.8 from a recently created D(Cs) model.

Covariance of engineering management characteristics with engineering employee performance

Science.gov (United States)

Hesketh, Andrew Arthur

1998-12-01

As business in the 1990's grapples with the impact of continuous improvement and quality to meet market demands, there is an increased need to improve the leadership capabilities of our managers. Engineers have indicated desire for certain managerial characteristics in their leadership but there have been no studies completed that approached the problem of determining what managerial characteristics were best at improving employee performance. This study addressed the idea of identifying certain managerial characteristics that enhance employee performance. In the early 1990's, McDonnell Douglas Aerospace in St. Louis used a forced distribution system and allocated 35% of its employees into a "exceeds expectations" category and 60% into a "meets expectations" category. A twenty-question 5 point Likert scale survey on managerial capabilities was administered to a sample engineering population that also obtained their "expectations" category. A single factor ANOVA on the survey results determined a statistical difference between the "exceeds" and "meets" employees with four of the managerial capability questions. The "exceeds expectations" employee indicated that supervision did a better job of supporting subordinate development, clearly communicating performance expectations, and providing timely performance feedback when compared to the "meets expectations" employee. The "meets expectations" employee felt that their opinions, when different from their supervisor's, were more often ignored when compared to the "exceeds expectations" employee. These four questions relate to two specific managerial characteristics, "gaining (informal) authority and support" or "control" characteristic and "providing assistance and guidance" or "command" characteristic, that can be emphasized in managerial training programs.

14 CFR 135.247 - Pilot qualifications: Recent experience.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 3 2010-01-01 2010-01-01 false Pilot qualifications: Recent experience... Flight Crewmember Requirements § 135.247 Pilot qualifications: Recent experience. (a) No certificate holder may use any person, nor may any person serve, as pilot in command of an aircraft carrying...

27 CFR 19.823 - Changes after original qualification.

Science.gov (United States)

2010-04-01

... 27 Alcohol, Tobacco Products and Firearms 1 2010-04-01 2010-04-01 false Changes after original... Vaporizing Process Qualification Documents § 19.823 Changes after original qualification. When there is a change in the information recorded in the original approved application, the proprietor shall make a...

Selection of equipment for equipment qualification

International Nuclear Information System (INIS)

Torr, K.G.

1989-01-01

This report describes the methodology applied in selecting equipment in the special safety systems for equipment qualification in the CANDU 600 MW nuclear generating stations at Gentilly 2 and Point Lepreau. Included is an explanation of the selection procedure adopted and the rationale behind the criteria used in identifying the equipment. The equipment items on the list have been grouped into three priority categories as a planning aid to AECB staff for a review of the qualification status of the special safety systems

An investigation of individual functionality football referees qualifications

Directory of Open Access Journals (Sweden)

S.M. Berezka

2014-12-01

Full Text Available Purpose: determine the level of individual functionality referees qualifications. Objective of the study was to determine the physiological parameters characterizing the functionality of football referees qualifications. Material : mainly experiment involved 29 highly qualified referees aged 21-45 years. In the main experiment participated 29 referees and 40 assistant referees (n = 69 Ukrainian Premier League. Results: found that the means and methods that use Ukrainian football referee high qualification in the special physical training for a competition, are not effective enough. Consequence of poorly planned training process is to increase the number of wrong decisions of the referees during the match associated with poor motor activity. Conclusions: data obtained in the course of educational research confirmed our theory about the necessity of individualization process special physical training qualifications of referees, which would entail increasing the functional and motor abilities of the referees, and as a consequence of better and successful completion of the work.

Buried Waste Program (BWP) data qualification manual

International Nuclear Information System (INIS)

Casey, C.; Larson, R.A.; Harris, G.A.

1989-06-01

The Data Qualification Manual (DQM) has been developed to discuss the process required to qualify data generated for the Buried Waste Program (BWP). The data from the BWP tasks conducted at the Radioactive Waste Management Complex (RWMC) and elsewhere will lead to remedial decisions being made which are governed by federal regulations administered by the Environmental Protection Agency (EPA). Data qualification is the process of insuring that only data of planned and known qualities are used to make a decision or answer a question. Although it is the Data Integrity Review Committee's (DIRC) responsibility to insure that the quality of all BWP data is ultimately verified and validated, all personnel who participate in the data gathering process will affect the quality of the data and must be responsible for knowing what is required to produce data of the planned quality. Therefore this manual is addressed to all participants in a data-gathering task. This manual discusses requirements to support data qualification in several areas, including: the sampling and analysis plan; data quality objectives and PARCC goals; sample custody documentation; quality assurance; assembly of the data qualification package; and existing data. 23 refs., 4 figs., 6 tabs

Component-Level Selection and Qualification for the Global Ecosystem Dynamics Investigation (GEDI) Laser Altimeter Transmitter

Science.gov (United States)

Frese, Erich A.; Chiragh, Furqan L.; Switzer, Robert; Vasilyev, Aleksey A.; Thomes, Joe; Coyle, D. Barry; Stysley, Paul R.

2018-01-01

Flight quality solid-state lasers require a unique and extensive set of testing and qualification processes, both at the system and component levels to insure the laser's promised performance. As important as the overall laser transmitter design is, the quality and performance of individual subassemblies, optics, and electro-optics dictate the final laser unit's quality. The Global Ecosystem Dynamics Investigation (GEDI) laser transmitters employ all the usual components typical for a diode-pumped, solid-state laser, yet must each go through their own individual process of specification, modeling, performance demonstration, inspection, and destructive testing. These qualification processes and results for the laser crystals, laser diode arrays, electro-optics, and optics, will be reviewed as well as the relevant critical issues encountered, prior to their installation in the GEDI flight laser units.

Cement waste form qualification report: WVDP [West Valley Demonstration Project] PUREX decontaminated supernatant

International Nuclear Information System (INIS)

McVay, C.W.; Stimmel, J.R.; Marchetti, S.

1988-08-01

This report provides a summary of work performed to develop a cement-based, low-level waste formulation suitable for the solidification of decontaminated high-level waste liquid produced as a by-product of PUREX spent fuel reprocessing. The resultant waste form is suitable for interim storage and is intended for ultimate disposal as low-level Class C waste; it also meets the stability requirements of the NRC Branch Technical Position on Waste Form Qualification, May 1983 and the requirements of 10 CFR 61. A recipe was developed utilizing only Portland Type I cement based on an inorganic salts simulant of the PUREX supernatant. The qualified recipe was tested full scale in the production facility and was observed to produce a product with entrained air, low density, and lower-than-expected compressive strength. Further laboratory scale testing with actual decontaminated supernatant revealed that set retarders were present in the supernatant, precluding setting of the product and allowing the production of ''bleed water.'' Calcium nitrate and sodium silicate were added to overcome the set retarding effect and produced a final product with improved performance when compared to the original formulation. This report describes the qualification process and qualification test results for the final product formulation. 7 refs., 38 figs., 21 tabs

Qualification, certification and training systems of a Japanese nuclear power plant supplier

International Nuclear Information System (INIS)

Yoshijima, S.; Tomita, J.; Yoneda, Y.

1982-01-01

Training and indoctrination of personnel are very important for performing quality assurance activities in nuclear power plants. The paper presents policies, procedures and practices with regard to a training system for site construction workers, a training system for plant operation personnel at a special facility, and services and activities for operating plants. The training system for site workers and technicians offers basic training for all workers, and special training and qualification for field welders, cable-termination workers and non-destructive examination personnel. In addition to the qualification system for field welders applied by the regulatory body, a privat-company qualification system exists. Also, a training centre for BWR operators has been established. This facility has a simulator duplicating the main control room of an actual plant and a computer-assisted instruction system. Standard training courses, short-term basic courses, re-training courses, group training courses and special training courses are held at the training centre. Finally, the services and activities performed by Toshiba Corporation for operating plants are described. These activities of the plant supplier aim at keeping up and further enhancing the safety and reliability of operating plants and mainly consist of: (1) collection and evaluation of plant operation data, with re-evaluation and improvement of systems and components; (2) development of new maintenance techniques; (3) development of measures for reducing annual outage periods; and (4) plant emergency preparedness. (author)

Performance of discrete heat engines and heat pumps in finite time

Science.gov (United States)

Feldmann; Kosloff

2000-05-01

The performance in finite time of a discrete heat engine with internal friction is analyzed. The working fluid of the engine is composed of an ensemble of noninteracting two level systems. External work is applied by changing the external field and thus the internal energy levels. The friction induces a minimal cycle time. The power output of the engine is optimized with respect to time allocation between the contact time with the hot and cold baths as well as the adiabats. The engine's performance is also optimized with respect to the external fields. By reversing the cycle of operation a heat pump is constructed. The performance of the engine as a heat pump is also optimized. By varying the time allocation between the adiabats and the contact time with the reservoir a universal behavior can be identified. The optimal performance of the engine when the cold bath is approaching absolute zero is studied. It is found that the optimal cooling rate converges linearly to zero when the temperature approaches absolute zero.

Engineering Performance of Polyurethane Bonded Aggregates

Directory of Open Access Journals (Sweden)

Haimin WU

2017-08-01

Full Text Available In this paper the engineering performance of polyurethane (PUR bonded aggregate were studied. The engineering performance, including compressive and flexural mechanical properties, void ratio, and coefficient of permeability were determined through laboratory tests. Moreover, the effects of two different curing conditions on the compressive strength properties of a PUR bonded aggregate were also evaluated. The compressive strengths of PUR bonded aggregates were found to be lower than that of conventional porous concrete, which is a commonly used cushion material. However, experimental results indicated a higher void ratio and coefficient of permeability, lower elasticity modulus, better toughness, and stronger adaptability to flexural deformation compared to porous concrete. Consequently, PUR bonded aggregate is a better solution than porous concrete when used as the cushion material of a geomembrane surface barrier for a high rock-fill dam.DOI: http://dx.doi.org/10.5755/j01.ms.23.2.15798

14 CFR 121.437 - Pilot qualification: Certificates required.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 3 2010-01-01 2010-01-01 false Pilot qualification: Certificates required... Pilot qualification: Certificates required. (a) No pilot may act as pilot in command of an aircraft (or... pilots) unless he holds an airline transport pilot certificate and an appropriate type rating for that...

14 CFR 125.285 - Pilot qualifications: Recent experience.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 3 2010-01-01 2010-01-01 false Pilot qualifications: Recent experience... Requirements § 125.285 Pilot qualifications: Recent experience. (a) No certificate holder may use any person, nor may any person serve, as a required pilot flight crewmember unless within the preceding 90...

Qualification Users' Perceptions and Experiences of Assessment Reliability

Science.gov (United States)

Chamberlain, Suzanne

2013-01-01

This paper presents the findings of a study designed to explore qualification users' perceptions and experiences of reliability in the context of national assessment outcomes in England. The study consisted of 17 focus groups conducted across six sectors of qualification users: students, teachers, trainee teachers, job-seekers, employers and…

Revision of the qualification framework at the Technical University of Denmark Part 2

DEFF Research Database (Denmark)

Henneberg, Kaj-Åge; Kuhn, Luise Theil; Jungersen, Gregers

2017-01-01

Using a revised Qualification Framework (QF) with four main categories: -to know, - to be, -to interact, and -to do, this paper demonstrates how to use the elements of the QF to construct Programme-Qualification Matrices. A general Programme- Qualification Matrix defines the qualifications and th...

Fire-safety engineering and performance-based codes

DEFF Research Database (Denmark)

Sørensen, Lars Schiøtt

project administrators, etc. The book deals with the following topics: • Historical presentation on the subject of fire • Legislation and building project administration • European fire standardization • Passive and active fire protection • Performance-based Codes • Fire-safety Engineering • Fundamental......Fire-safety Engineering is written as a textbook for Engineering students at universities and other institutions of higher education that teach in the area of fire. The book can also be used as a work of reference for consulting engineers, Building product manufacturers, contractors, building...... thermodynamics • Heat exchange during the fire process • Skin burns • Burning rate, energy release rate and design fires • Proposal to Risk-based design fires • Proposal to a Fire scale • Material ignition and flame spread • Fire dynamics in buildings • Combustion products and toxic gases • Smoke inhalation...

Adaptation Method for Overall and Local Performances of Gas Turbine Engine Model

Science.gov (United States)

Kim, Sangjo; Kim, Kuisoon; Son, Changmin

2018-04-01

An adaptation method was proposed to improve the modeling accuracy of overall and local performances of gas turbine engine. The adaptation method was divided into two steps. First, the overall performance parameters such as engine thrust, thermal efficiency, and pressure ratio were adapted by calibrating compressor maps, and second, the local performance parameters such as temperature of component intersection and shaft speed were adjusted by additional adaptation factors. An optimization technique was used to find the correlation equation of adaptation factors for compressor performance maps. The multi-island genetic algorithm (MIGA) was employed in the present optimization. The correlations of local adaptation factors were generated based on the difference between the first adapted engine model and performance test data. The proposed adaptation method applied to a low-bypass ratio turbofan engine of 12,000 lb thrust. The gas turbine engine model was generated and validated based on the performance test data in the sea-level static condition. In flight condition at 20,000 ft and 0.9 Mach number, the result of adapted engine model showed improved prediction in engine thrust (overall performance parameter) by reducing the difference from 14.5 to 3.3%. Moreover, there was further improvement in the comparison of low-pressure turbine exit temperature (local performance parameter) as the difference is reduced from 3.2 to 0.4%.

Questions of qualification exam for non-destructive testing and materials science - the first level

International Nuclear Information System (INIS)

Shaaban, H.I.; Addarwish, J.M.A.

2013-01-01

The book contains seven chapters: Questions of qualification for magnetic particles testing method - Questions of qualification for liquids penetrant testing method - Questions of qualification for the visual inspection testing method - Questions of qualification for the ultrasonic testing method - Questions of qualification for the eddy current testing method - Questions of rehabilitation for industrial radiographic testing method - Qualification questions about materials science and manufacturing defects of castings and welding and comparison between non-destructive testing methods.

Effect of temperature change at inlet of engine on the corrected performance of turbofan engine

Energy Technology Data Exchange (ETDEWEB)

Kozu, Masao; Yajima, Satoshi [Defence Agency, Tokyo, JapanIshikawajima-Harima Heavy Industries Co. Ltd., Tokyo (Japan)

1989-06-10

Theoretical consideration on the effect of inlet temperature change of engine on the engine performance was conducted, and soundness of the result was appreciated by applying it to the experimental result of turbofan engine. As the theoretical consideration, premises of Buckingham's fundamental theorem was corrected by Reynolds Number and by the consideration on the effect of inlet temperature on gas constant and specific heat ratio. By using the result, correction factors were calculated from the experimental result of an actual turbo-fan engine. The correction factors were applied to the other engine test result and confirmed satisfactory soundness. 4 refs., 11 figs.

Seismic qualification of existing nuclear installations in India - a proposal

International Nuclear Information System (INIS)

Basu, P.C.

2001-01-01

In India, the work toward seismic qualification of existing nuclear facilities has been started. Preliminary work is being undertaken with respect to identifying the facilities which would be taken up for seismic qualification, approach and methodology for re-evaluation for seismic safety, acceptance criteria, etc. Work has also been started for framing up the criteria and methodology of the seismic qualification of these facilities. Present paper contains the proposal in this respect. This proposal is on similar lines of the present practice of seismic qualification of NPP, as summarized in the Appendix, but has been modified to suit the special requirements of Indian nuclear installations. (author)

Analysis of Expectations of Forest Products Industry from Forest Industry Engineering Education

OpenAIRE

GEDİK, Tarık; ÇİL, Muhammet; SEVİM KORKUT, Derya; CEMİL AKYÜZ, Kadri; KOŞAR, Gökşen; BEKAR, İlter

2016-01-01

Forest industry engineers, representing the qualified labor within the forest products industry, choose their field of study either deliberately or by chance. This study explores the main skill sets of forest industry engineers required by forest products industry. As representatives of forest industry owner of forest products companies were surveyed about their views on the qualifications a forest industry engineer must have.This study covered total 7111 companies registered to TOBB as a for...

Performance and exhaust emissions of a biodiesel engine

Energy Technology Data Exchange (ETDEWEB)

Canakci, Mustafa [Kocaeli University, Technical Education Faculty, 41380 Kocaeli (Turkey); Erdil, Ahmet [Kocaeli University, Engineering Faculty, 41040 Kocaeli (Turkey); Arcaklioglu, Erol [Kirikkale University, Engineering Faculty, 71450 Kirikkale (Turkey)

2006-06-15

In this study, the applicabilities of Artificial Neural Networks (ANNs) have been investigated for the performance and exhaust-emission values of a diesel engine fueled with biodiesels from different feedstocks and petroleum diesel fuels. The engine performance and emissions characteristics of two different petroleum diesel-fuels (No. 1 and No. 2), biodiesels (from soybean oil and yellow grease), and their 20% blends with No. 2 diesel fuel were used as experimental results. The fuels were tested at full load (100%) at 1400-rpm engine speed, where the engine torque was 257.6Nm. To train the network, the average molecular weight, net heat of combustion, specific gravity, kinematic viscosity, C/H ratio and cetane number of each fuel are used as the input layer, while outputs are the brake specific fuel-consumption, exhaust temperature, and exhaust emissions. The back-propagation learning algorithm with three different variants, single layer, and logistic sigmoid transfer function were used in the network. By using weights in the network, formulations have been given for each output. The network has yielded R{sup 2} values of 0.99 and the mean % errors are smaller than 4.2 for the training data, while the R{sup 2} values are about 0.99 and the mean % errors are smaller than 5.5 for the test data. The performance and exhaust emissions from a diesel engine, using biodiesel blends with No. 2 diesel fuel up to 20%, have been predicted using the ANN model. sing the ANN model. (author)

14 CFR 121.439 - Pilot qualification: Recent experience.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 3 2010-01-01 2010-01-01 false Pilot qualification: Recent experience. 121... Pilot qualification: Recent experience. (a) No certificate holder may use any person nor may any person serve as a required pilot flight crewmember, unless within the preceding 90 days, that person has made...

32 CFR 935.139 - Motor vehicle operator qualifications.

Science.gov (United States)

2010-07-01

... 32 National Defense 6 2010-07-01 2010-07-01 false Motor vehicle operator qualifications. 935.139... AND INSULAR REGULATIONS WAKE ISLAND CODE Motor Vehicle Code § 935.139 Motor vehicle operator qualifications. (a) No person may operate a privately owned motor vehicle on Wake Island unless he has an island...

High Performance Computing in Science and Engineering '14

CERN Document Server

Kröner, Dietmar; Resch, Michael

2015-01-01

This book presents the state-of-the-art in supercomputer simulation. It includes the latest findings from leading researchers using systems from the High Performance Computing Center Stuttgart (HLRS). The reports cover all fields of computational science and engineering ranging from CFD to computational physics and from chemistry to computer science with a special emphasis on industrially relevant applications. Presenting findings of one of Europe’s leading systems, this volume covers a wide variety of applications that deliver a high level of sustained performance. The book covers the main methods in high-performance computing. Its outstanding results in achieving the best performance for production codes are of particular interest for both scientists and   engineers. The book comes with a wealth of color illustrations and tables of results.  

Qualification of NDT techniques for in-service inspections in nuclear power plants in accordance with ENIQ - examples and lessons - learned

International Nuclear Information System (INIS)

Just, T.; Csapo, G.

2006-01-01

ENIQ (European Network for Inspection and Qualification) has developed regulations on how to qualify non-destructive testing (NDT) methods and techniques in a standardized and structured manner. Two major innovative qualifications were carried out and reviewed with regard to implementation, according to the recommended German practice of ENIQ. The conclusions were drawn after performing the ENIQ qualification procedure for in-service inspections (ISI) of real components in nuclear power plants (NPP). The first example covers the qualification of NDT methods for the detection and characterization of surface, subsurface and underclad cracks in the area of the austenitic cladded RPV surface. Open and blind tests were conducted applying UT and ET (from the ID) and UT (from the OD) on realistic flaws (artificially induced IGSCC, hot cracks and fatigue cracks) in the cladding of a full scale RPV mock-up from MPA Stuttgart. The second example covers the qualification of mechanised RT in combination with tomography (developed by the BAM) for the sizing of cracks in pipe welds. For both qualification procedures TUEV NORD SysTec experts were part of the qualification body. The proposed NDT procedures have been qualified within defined limits of application. Recommendations were made to optimise the procedures and the techniques itself further. (orig.)

A review on the engine performance and exhaust emission characteristics of diesel engines fueled with biodiesel blends.

Science.gov (United States)

Damanik, Natalina; Ong, Hwai Chyuan; Tong, Chong Wen; Mahlia, Teuku Meurah Indra; Silitonga, Arridina Susan

2018-06-01

Biodiesels have gained much popularity because they are cleaner alternative fuels and they can be used directly in diesel engines without modifications. In this paper, a brief review of the key studies pertaining to the engine performance and exhaust emission characteristics of diesel engines fueled with biodiesel blends, exhaust aftertreatment systems, and low-temperature combustion technology is presented. In general, most biodiesel blends result in a significant decrease in carbon monoxide and total unburned hydrocarbon emissions. There is also a decrease in carbon monoxide, nitrogen oxide, and total unburned hydrocarbon emissions while the engine performance increases for diesel engines fueled with biodiesels blended with nano-additives. The development of automotive technologies, such as exhaust gas recirculation systems and low-temperature combustion technology, also improves the thermal efficiency of diesel engines and reduces nitrogen oxide and particulate matter emissions.

Rotary engine performance computer program (RCEMAP and RCEMAPPC): User's guide

Science.gov (United States)

Bartrand, Timothy A.; Willis, Edward A.

1993-01-01

This report is a user's guide for a computer code that simulates the performance of several rotary combustion engine configurations. It is intended to assist prospective users in getting started with RCEMAP and/or RCEMAPPC. RCEMAP (Rotary Combustion Engine performance MAP generating code) is the mainframe version, while RCEMAPPC is a simplified subset designed for the personal computer, or PC, environment. Both versions are based on an open, zero-dimensional combustion system model for the prediction of instantaneous pressures, temperature, chemical composition and other in-chamber thermodynamic properties. Both versions predict overall engine performance and thermal characteristics, including bmep, bsfc, exhaust gas temperature, average material temperatures, and turbocharger operating conditions. Required inputs include engine geometry, materials, constants for use in the combustion heat release model, and turbomachinery maps. Illustrative examples and sample input files for both versions are included.

Improving human performance in maintenance personnel

International Nuclear Information System (INIS)

Gonzalez Anez, Francisco; Agueero Agueero, Jorge

2010-01-01

The continuous evolution and improvement of safety-related processes has included the analysis, design and development of training plans for the qualification of maintenance nuclear power plant personnel. In this respect, the international references in this area recommend the establishment of systematic qualification programmes for personnel performing functions or carrying out safety related tasks. Maintenance personnel qualification processes have improved significantly, and training plans have been designed and developed based on Systematic Approach to Training methodology to each job position. These improvements have been clearly reflected in recent training programmes with new training material and training facilities focused not only on developing technical knowledge and skills but also on improving attitudes and safety culture. The objectives of maintenance training facilities such as laboratories, mock-ups real an virtual, hydraulic loops, field simulators and other training material to be used in the maintenance training centre are to cover training necessities for initial and continuous qualification. Evidently, all these improvements made in the qualification of plant personnel should be extended to include supplemental personnel (external or contracted) performing safety-related tasks. The supplemental personnel constitute a very spread group, covering the performance of multiple activities entailing different levels of responsibility. Some of these activities are performed permanently at the plant, while others are occasional or sporadic. In order to establish qualification requirements for these supplemental workers, it is recommended to establish a rigorous analysis of job positions and tasks. The objective will be to identify the qualification requirements to assure competence and safety. (authors)

Effect of finite heat input on the power performance of micro heat engines

International Nuclear Information System (INIS)

Khu, Kerwin; Jiang, Liudi; Markvart, Tom

2011-01-01

Micro heat engines have attracted considerable interest in recent years for their potential exploitation as micro power sources in microsystems and portable devices. Thermodynamic modeling can predict the theoretical performance that can be potentially achieved by micro heat engine designs. An appropriate model can not only provide key information at the design stage but also indicate the potential room for improvement in existing micro heat engines. However, there are few models reported to date which are suitable for evaluating the power performance of micro heat engines. This paper presents a new thermodynamic model for determining the theoretical limit of power performance of micro heat engines with consideration to finite heat input and heat leakage. By matching the model components to those of a representative heat engine layout, the theoretical power, power density, and thermal efficiency achievable for a micro heat engine can be obtained for a given set of design parameters. The effects of key design parameters such as length and thermal conductivity of the engine material on these theoretical outputs are also investigated. Possible trade-offs among these performance objectives are discussed. Performance results derived from the developed model are compared with those of a working micro heat engine (P3) as an example. -- Highlights: → Thermodynamic model for micro heat engines. → Effect of different parameters on potential performance. → Tradeoffs for determining optimal size of micro engines.

On the way of only one fundamental information layer for everything within new paradigm sense; ecosystem qualification mapping

Directory of Open Access Journals (Sweden)

Kürşad Özkan

2016-07-01

Full Text Available The study was carried out to attract attention to the importance of holistic approach in ecological research studies and provide information about ecosystem qualification mapping, the fundamental layer for ecosystem-based management plans, by means of a case study example. In the study, species richness, potential energy footprint, resilience, rarity and dissimilarity were accepted as qualification components and the statistical analysis was performed by using 107 sample plot data taken from Yazılı Canyon Nature Park, located in the transition zone of the Mediterranean region, Turkey. All components were calculated for each sample plot. Then, Principle Component Analysis (PCA was applied to the components. As a result of the PCA applied, it was found that all components, except for dissimilarity, correspond with each other. Therefore, the formula for qualification index was created by taking species richness, potential energy footprint, resilience and rarity components into consideration. At the second phase of the study, qualification index and the dissimilarity component were modeled according to environmental factors taken as explanatory variables by using regression tree technique. With the regression tree models obtained, distribution maps of qualification index and the dissimilarity component were formed and group distinctions of the maps were drawn. Finally, by combining the groups of qualification index and the dissimilarity components, numerical values were assigned to the newly combined groups by using if-then rules. Thus, ecosystem based qualification value map of Yazılı Canyon Nature Park was formed.

Final Report: Performance Engineering Research Institute

Energy Technology Data Exchange (ETDEWEB)

Mellor-Crummey, John [Rice Univ., Houston, TX (United States)

2014-10-27

This document is a final report about the work performed for cooperative agreement DE-FC02-06ER25764, the Rice University effort of Performance Engineering Research Institute (PERI). PERI was an Enabling Technologies Institute of the Scientific Discovery through Advanced Computing (SciDAC-2) program supported by the Department of Energy's Office of Science Advanced Scientific Computing Research (ASCR) program. The PERI effort at Rice University focused on (1) research and development of tools for measurement and analysis of application program performance, and (2) engagement with SciDAC-2 application teams.

Global Trend In The Qualifications Of Medical Educators | Issa ...

African Journals Online (AJOL)

NPMCN) or its equivalents is the highest educational and professional qualification of clinical Medical Educators in Nigeria while PhD is the acceptable highest qualification for their basic medical sciences counterparts. This had been the status ...

Further developments in performance prediction techniques of adiabatic diesel engines

Energy Technology Data Exchange (ETDEWEB)

Rasihhan, Y

1990-01-01

The engine cycle simulation program 'SPICE', developed at Bath University, has been used extensively for insulated diesel engine research. The present study introduces more comprehensive engine heat transfer models thus enabling us to study the insulated engine heat transfer and performance characteristics in more detail. The new version of 'SPICE' separates the gas to wall heat transfer into two parts, convective and radiative. For this purpose, a detailed radiative heat transfer model which considers both the flame (gas and soot) and wall to wall radiative heat transfer is written. The previous engine resistance model is refined and replaced by a more detailed resistance model which considers piston-liner conduction heat transfer and 2-D heat flow in the liner. The wall surface temperature swing is also included in the engine heat transfer calculations which is quite significant in low conductivity ceramic insulated engines. A 1-D finite difference model is written for the transient heat transfer region of the wall and linked to the engine resistance model. This new version of 'SPICE' is used to predict the insulated engine heat transfer and performance for the experimental Petter PH1W engine for various insulation levels and schemes. An answer to the controversy of increase in engine heat loss with insulation is looked for. The effect of wall deposits on engine heat transfer and its significance for the insulated engine is highlighted. (Author).

Seismic qualification of a commercial grade emergency diesel generator system in high seismic zones

International Nuclear Information System (INIS)

Khan, Mohsin R.; Chen, Wayne W.H.; Chu, Winnie S.

2004-01-01

The paper presents the seismic qualification of a commercially procured emergency diesel generator (EDG) system for use in a nuclear power plant. Response spectrum analyses of finite element models, validated using in situ vibration test data, were performed to qualify the skid and floor mounted mechanical components whose functional capacity and structural integrity can be analyzed. Time history analyses of these models were also performed to obtain the amplified response spectra for seismic testing of small valves, electrical and electro-mechanical components whose functional capacity can not be analyzed to establish the seismic qualification. The operational loads were obtained by in-plant vibration monitoring. Full scale shake table testing was performed for auxiliary electrical cabinets. It is concluded that with some minor structural modifications, a commercial grade EDG system can be qualified for safety-related applications in nuclear power plants located in high seismic zones. (author)

Assessing mathematics within advanced school science qualifications

OpenAIRE

McAlinden, Mary; Noyes, Andrew

2017-01-01

Following sustained discussion regarding the relationship between advanced mathematics and science learning in England, the government has pursued a reform agenda in which mathematics is embedded in national, high stakes A-level science qualifications and their assessments for 18-year-olds. For example, A-level Chemistry must incorporate the assessment of relevant mathematics for at least 20% of the qualification. Other sciences have different mandated percentages. This embedding policy is ru...

Effect of biodiesel blends on engine performance and exhaust emission for diesel dual fuel engine

International Nuclear Information System (INIS)

Mohsin, R.; Majid, Z.A.; Shihnan, A.H.; Nasri, N.S.; Sharer, Z.

2014-01-01

Highlights: • Engine and emission characteristics of biodiesel DDF engine system were measured. • Biodiesel DDF fuelled system produced high engine performance. • Lower hydrocarbons and carbon dioxide was emitted by biodiesel DDF system. • Biodiesel DDF produced slightly higher carbon monoxide and nitric oxides emission. - Abstract: Biodiesel derived from biomass is a renewable source of fuel. It is renovated to be the possible fuel to replace fossil derived diesel due to its properties and combustion characteristics. The integration of compressed natural gas (CNG) in diesel engine known as diesel dual fuel (DDF) system offered better exhaust emission thus become an attractive option for reducing the pollutants emitted from transportation fleets. In the present study, the engine performance and exhaust emission of HINO H07C DDF engine; fuelled by diesel, biodiesel, diesel–CNG, and biodiesel–CNG, were experimentally studied. Biodiesel and diesel fuelled engine system respectively generated 455 N m and 287 N m of torque. The horse power of biodiesel was found to be 10–20% higher compared to diesel. Biodiesel–CNG at 20% (B20-DDF) produced the highest engine torque compared to other fuel blends Biodiesel significantly increase the carbon monoxide (15–32%) and nitric oxides (6.67–7.03%) but in contrast reduce the unburned hydrocarbons (5.76–6.25%) and carbon dioxide (0.47–0.58%) emissions level. These results indicated that biodiesel could be used without any engine modifications as an alternative and environmentally friendly fuel especially the heavy transportation fleets

Adjusting the specificity of an engine map based on the sensitivity of an engine control parameter relative to a performance variable

Science.gov (United States)

Jiang, Li; Lee, Donghoon; Yilmaz, Hakan; Stefanopoulou, Anna

2014-10-28

Methods and systems for engine control optimization are provided. A first and a second operating condition of a vehicle engine are detected. An initial value is identified for a first and a second engine control parameter corresponding to a combination of the detected operating conditions according to a first and a second engine map look-up table. The initial values for the engine control parameters are adjusted based on a detected engine performance variable to cause the engine performance variable to approach a target value. A first and a second sensitivity of the engine performance variable are determined in response to changes in the engine control parameters. The first engine map look-up table is adjusted when the first sensitivity is greater than a threshold, and the second engine map look-up table is adjusted when the second sensitivity is greater than a threshold.

Multivariate Analysis of Students' Performance in Math Courses and Specific Engineering Courses

OpenAIRE

H. Naccache; R. Hleiss

2016-01-01

The aim of this research is to study the relationship between the performance of engineering students in different math courses and their performance in specific engineering courses. The considered courses are taken mainly by engineering students during the first two years of their major. Several factors are being studied, such as gender and final grades in the math and specific engineering courses. Participants of this study comprised a sample of more than thousands of engineering students a...

An experimental study of the effect of octane number higher than engine requirement on the engine performance and emissions

Energy Technology Data Exchange (ETDEWEB)

Sayin, Cenk; Kilicaslan, Ibrahim; Canakci, Mustafa; Ozsezen, Necati [Kocaeli Univ., Dept. of Mechanical Education, Izmit (Turkey)

2005-06-01

In this study, the effect of using higher-octane gasoline than that of engine requirement on the performance and exhaust emissions was experimentally studied. The test engine chosen has a fuel system with carburettor because 60% of the vehicles in Turkey are equipped with the carburettor. The engine, which required 91-RON (Research Octane Number) gasoline, was tested using 95-RON and 91-RON. Results show that using octane ratings higher than the requirement of an engine not only decreases engine performance but also increases exhaust emissions. (Author)

Performance Testing of Diesel Engine using Cardanol-Kerosene oil blend

Directory of Open Access Journals (Sweden)

Ravindra

2018-01-01

Full Text Available Awareness of environmental pollution and fossil fuel depletion has necessitated the use of biofuels in engines which have a relatively cleaner emissions. Cardanol is a biofuel, abundantly available in India, which is a by-product of cashew processing industries. In this study performance of raw Cardanol blended with kerosene has been tested in diesel engine. Volumetric blend BK30 (30% kerosene and 70% Cardanol has been used for the test. The properties like flash point, viscosity and calorific value of the blend have been determined. The test was carried out in four stroke diesel engine connected with an eddy current dynamometer. Performance of the engine has been analysed by finding the brake specific fuel consumption (BSFC and brake thermal efficiency (BTE. The results showed that the brake thermal efficiency of the blend is 29.87%, with less CO and smoke emission compared to diesel. The results were also compared with the performance of Cardanol diesel blend and Cardanol camphor oil blend, which were already tested in diesel engines by other researchers. Earlier research work reveals that the blend of 30% camphor oil and 70% Cardanol performs very closer to diesel fuel with a thermal efficiency of 29.1%. Similarly, higher brake thermal efficiency was obtained for 20% Cardanol and 80% diesel blend.

Investigating the effects of LPG on spark ignition engine combustion and performance

International Nuclear Information System (INIS)

Bayraktar, Hakan; Durgun, Orhan

2005-01-01

A quasi-dimensional spark ignition (SI) engine cycle model is used to predict the cycle, performance and exhaust emissions of an automotive engine for the cases of using gasoline and LPG. Governing equations of the mathematical model mainly consist of first order ordinary differential equations derived for cylinder pressure and temperature. Combustion is simulated as a turbulent flame propagation process and during this process, two different thermodynamic regions consisting of unburned gases and burned gases that are separated by the flame front are considered. A computer code for the cycle model has been prepared to perform numerical calculations over a range of engine speeds and fuel-air equivalence ratios. In the computations performed at different engine speeds, the same fuel-air equivalence ratios are selected for each fuel to make realistic comparisons from the fuel economy and fuel consumption points of view. Comparisons show that if LPG fueled SI engines are operated at the same conditions with those of gasoline fueled SI engines, significant improvements in exhaust emissions can be achieved. However, variations in various engine performance parameters and the effects on the engine structural elements are not promising

Qualification of Electrical Components in Nuclear Power Plants. Management of Ageing

Energy Technology Data Exchange (ETDEWEB)

Spaang, Kjell [Ingemansson Technology AB, Goeteborg (Sweden); Staahl, Gunnar [Westinghouse Atom, Vaesteraas (Sweden)

2002-05-01

This report reviews R and D results and experiences forming the bases for the preparation of a report on management of ageing. It includes basic information and descriptions of value for persons who work with the questions and some data from investigations of the ageing characteristics of various materials: limit levels, dose-rate effects, activation energies, methods for condition monitoring, etc. This report is restricted to safety related components containing ageing sensitive parts, mainly organic materials (polymers). For components located in the containment, the possibilities of continuous supervision are limited. The accessibility for regular inspections is also limited in many cases. Therefore, the main part of this report deals with the qualification of such components. In addition, some material is given on qualification located outside containment with better possibilities for frequent inspection and supervision. A survey is made of activities, programs and tools for ageing qualification in connection with initial environmental qualification (type testing) as well as after installation (condition monitoring, extension of qualified life through on-going qualification). Tools are also given for supplementary ageing qualification of already installed components.

Qualification of Electrical Components in Nuclear Power Plants. Management of Ageing

International Nuclear Information System (INIS)

Spaang, Kjell; Staahl, Gunnar

2002-05-01

This report reviews R and D results and experiences forming the bases for the preparation of a report on management of ageing. It includes basic information and descriptions of value for persons who work with the questions and some data from investigations of the ageing characteristics of various materials: limit levels, dose-rate effects, activation energies, methods for condition monitoring, etc. This report is restricted to safety related components containing ageing sensitive parts, mainly organic materials (polymers). For components located in the containment, the possibilities of continuous supervision are limited. The accessibility for regular inspections is also limited in many cases. Therefore, the main part of this report deals with the qualification of such components. In addition, some material is given on qualification located outside containment with better possibilities for frequent inspection and supervision. A survey is made of activities, programs and tools for ageing qualification in connection with initial environmental qualification (type testing) as well as after installation (condition monitoring, extension of qualified life through on-going qualification). Tools are also given for supplementary ageing qualification of already installed components

Empowering Engineering Students through Employability Skills

Directory of Open Access Journals (Sweden)

Urvashi Kaushal

2016-12-01

Full Text Available A professional course like engineering strives to get maximum number of its students placed through campus interviews. While communication skills have been added in all the engineering courses with the aim to improve their performance in placement, the syllabus mostly concentrates on the development of four language skills. The students are not made aware of the employability skills and their significance. the increasing competition makes it imperative that apart from a regular degree certain skills are required by engineers. Industries while advertising for various posts even mention essential skills required along with the essential qualification. However skills and the significance of skills while applying for jobs or while facing interviews is a topic which is rarely given consideration while preparing for job interviews or while entering the job market. This paper intends to enlist the importance of skills and why students need to be aware of the skills they possess and how they can work on packaging their candidature around a few skills.  Different profession requires different skills and if students identify their skills or acquire certain skills they can unquestionably have an added advantage in the interview and placement. Hence, this paper intends to enlist the skills, the importance of skills, ways to create awareness of individual skills specifically in engineering students who will step into the industry in near future.

Transient performance simulation of aircraft engine integrated with fuel and control systems

International Nuclear Information System (INIS)

Wang, C.; Li, Y.G.; Yang, B.Y.

2017-01-01

Highlights: • A new performance simulation method for engine hydraulic fuel systems is introduced. • Time delay of engine performance due to fuel system model is noticeable but small. • The method provides details of fuel system behavior in engine transient processes. • The method could be used to support engine and fuel system designs. - Abstract: A new method for the simulation of gas turbine fuel systems based on an inter-component volume method has been developed. It is able to simulate the performance of each of the hydraulic components of a fuel system using physics-based models, which potentially offers more accurate results compared with those using transfer functions. A transient performance simulation system has been set up for gas turbine engines based on an inter-component volume (ICV) method. A proportional-integral (PI) control strategy is used for the simulation of engine controller. An integrated engine and its control and hydraulic fuel systems has been set up to investigate their coupling effect during engine transient processes. The developed simulation system has been applied to a model aero engine. The results show that the delay of the engine transient response due to the inclusion of the fuel system model is noticeable although relatively small. The developed method is generic and can be applied to any other gas turbines and their control and fuel systems.

Economies of using seismic experience data qualification methods at Department of Energy facilities

International Nuclear Information System (INIS)

Loceff, F.; Antaki, G.; Goen, L.

1995-01-01

This paper summarizes the implementation of the seismic qualification of existing equipment using experience data techniques. The emphasis is on the economies of this approach compared with standard qualification methods of analysis and testing or replacement with qualified equipment. Seismic qualification of existing equipment using experience data is a technical necessity and is the most economically attractive of the options. Representative costs for seismic qualification at two facilities show costs are substantially lower than the costs for qualification using conventional methods. Because of the experience to date, the authors recommend that the Department of Energy continue to sponsor the Existing Facilities Program for applying qualification using experience data techniques at DOE facilities

Qualifications of Subject Teachers in Special Education Schools

Science.gov (United States)

Rasmussen, Meryem Uçar; Kis, Arzu

2018-01-01

Teacher qualifications are essential to be able to teach children with special needs efficiently. Therefore the aim of this study is to determine the qualifications of subject teachers in special education schools in Turkey. In the study 20 subject teachers within the field of music, art and sports who worked in special education schools in Turkey…

14 CFR 121.909 - Approval of Advanced Qualification Program.

Science.gov (United States)

2010-01-01

... criteria. Each AQP must have separate curriculums for indoctrination, qualification, and continuing... the training and evaluation of CRM and technical skills and knowledge. An application for approval of... must meet all the requirements of this subpart. (2) Each indoctrination, qualification, and continuing...

Helicopter Gas Turbine Engine Performance Analysis : A Multivariable Approach

NARCIS (Netherlands)

Arush, Ilan; Pavel, M.D.

2017-01-01

Helicopter performance relies heavily on the available output power of the engine(s) installed. A simplistic single-variable analysis approach is often used within the flight-testing community to reduce raw flight-test data in order to predict the available output power under different atmospheric

Comparative performance analysis of combined-cycle pulse detonation turbofan engines (PDTEs

Directory of Open Access Journals (Sweden)

Sudip Bhattrai

2013-09-01

Full Text Available Combined-cycle pulse detonation engines are promising contenders for hypersonic propulsion systems. In the present study, design and propulsive performance analysis of combined-cycle pulse detonation turbofan engines (PDTEs is presented. Analysis is done with respect to Mach number at two consecutive modes of operation: (1 Combined-cycle PDTE using a pulse detonation afterburner mode (PDA-mode and (2 combined-cycle PDTE in pulse detonation ramjet engine mode (PDRE-mode. The performance of combined-cycle PDTEs is compared with baseline afterburning turbofan and ramjet engines. The comparison of afterburning modes is done for Mach numbers from 0 to 3 at 15.24 km altitude conditions, while that of pulse detonation ramjet engine (PDRE is done for Mach 1.5 to Mach 6 at 18.3 km altitude conditions. The analysis shows that the propulsive performance of a turbine engine can be greatly improved by replacing the conventional afterburner with a pulse detonation afterburner (PDA. The PDRE also outperforms its ramjet counterpart at all flight conditions considered herein. The gains obtained are outstanding for both the combined-cycle PDTE modes compared to baseline turbofan and ramjet engines.

Simulating Effects of High Angle of Attack on Turbofan Engine Performance

Science.gov (United States)

Liu, Yuan; Claus, Russell W.; Litt, Jonathan S.; Guo, Ten-Huei

2013-01-01

A method of investigating the effects of high angle of attack (AOA) flight on turbofan engine performance is presented. The methodology involves combining a suite of diverse simulation tools. Three-dimensional, steady-state computational fluid dynamics (CFD) software is used to model the change in performance of a commercial aircraft-type inlet and fan geometry due to various levels of AOA. Parallel compressor theory is then applied to assimilate the CFD data with a zero-dimensional, nonlinear, dynamic turbofan engine model. The combined model shows that high AOA operation degrades fan performance and, thus, negatively impacts compressor stability margins and engine thrust. In addition, the engine response to high AOA conditions is shown to be highly dependent upon the type of control system employed.

42 CFR 21.47 - Examination; anticipation of meeting qualifications.

Science.gov (United States)

2010-10-01

... 42 Public Health 1 2010-10-01 2010-10-01 false Examination; anticipation of meeting qualifications. 21.47 Section 21.47 Public Health PUBLIC HEALTH SERVICE, DEPARTMENT OF HEALTH AND HUMAN SERVICES PERSONNEL COMMISSIONED OFFICERS Appointment § 21.47 Examination; anticipation of meeting qualifications. A...

Effects of Reynold's number on flight performance of turbofan engine

Energy Technology Data Exchange (ETDEWEB)

Kozu, Masao; Yajima, Satoshi [Defense Agency Tokyo (Japan); Ishikawajima-Harima Heavy Industries Co. Ltd., Tokyo (Japan))

1988-12-10

Concerning the performance of the F3-30 turbofan engine which is carried on the intermediate trainer XT-4 of the Air Self Defense Force, tests simulating its flight conditions were conducted at the Altitude Test Facility (ATF) of the Arnold Engineering Development Center (AEDC), U.S. Air Force in order to adjust the effect of Reynold's number corresponding to the flight condition. This report summarizes the results of the above tests. As the results of the tests, it was revealed that in order to calculate with precision the flight performance of the F3-30 turbofan engine, it was required to adjust Reynold's number against the following figures, namely the fan air flow, compressor air flow, compressor adiabatic efficiency, low pressure turbine gas flow and low pressure turbine adiabatic efficiency. The engine performance calculated by using the above adjustments agreed well with the measured values of the ATF tests. 7 refs., 17 figs., 1 tab.

Manufacturing pre-qualification of a Short Breeder Unit mockup (SHOBU) as part of the roadmap toward the out-of-pile validation of a full scale Helium Cooled Pebble Bed Breeder Unit

International Nuclear Information System (INIS)

Hernández, Francisco A.; Rey, Jorg; Neuberger, Heiko; Krasnorutskyi, Sergii; Niewöhner, Reinhard; Felde, Alexander

2015-01-01

Highlights: • A relevant mockup of a HCPB Breeder Unit for ITER (SHOBU) has been manufactured. • The manufacturing technologies used in SHOBU and its assembly sequence are reported. • Preliminary qualification of the welds has been successfully done after codes. • Future work foreseen to manufacture a feasibility mockup according to RCC-MRx code. - Abstract: The key components of the Helium Cooled Pebble Bed Test Blanket Module (HCPB TBM) in ITER are the Breeder Units (BU). These are the responsible for the tritium breeding and part of the heat extraction in the HCPB TBM. After a detailed design and engineering phase performed during the last years in the Karlsruhe Institute of Technology (KIT), a reference model for the manufacturing of a HCPB BU mock-up has been obtained. The mid-term is the out-of-pile qualification of the thermal and thermo-mechanical performance of a full-scale HCPB BU mock-up in a dedicated helium loop. Several key manufacturing technologies have been developed for the fabrication of the HCPB BU. In order to pre-qualify these techniques, a Short Breeder Unit mock-up (SHOBU) is under construction and to be tested. This paper aims at describing the relevance of SHOBU with a full-scale HCPB BU, the constitutive parts of SHOBU, the manufacturing and joining technologies involved, the assembly sequence (taking into consideration functional steps like its filling with Li_4SiO_4 pebbles or its assembly in the HCPB TBM) and the welding procedures studied. The paper concludes with a description of the required pre-qualification tests performed to SHOBU, i.e. pressure and leak tightness tests, according to the standards.

Environmental Qualification Program for NPP Krsko

International Nuclear Information System (INIS)

Cerjak, J.; Klenovsek, P.; Pavsek, J.; Spalj, S.; Colovic, G.

1998-01-01

The functionality the equipment important to safety is deteriorated during its service due to ageing and harsh environment conditions. Since the environment is a potential for common cause failures, the purpose of Environmental Qualification (EQ) is to demonstrate the capability of safety-related equipment to perform its safety function in aged conditions and under extreme conditions after design bases event (DBE). EQ is one of the steps in licensing process according to US regulatory documents and standards (10CFR50.49, RG 1.89, NUREG-0588, IEEE-323). This paper presents the efforts in establishing the EQ program in the Krsko nuclear power plant. (author)

Report on survey in fiscal 2000. Survey on introduction of external accreditation system in engineer education (civil engineering); 2000 nendo chosa hokokusho. Gijutsusha kyoiku no gaibu ninteiseido donyu ni kansuru chosa (Doboku)

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-03-01

In order to ensure international applicability of engineer education such as in universities and other organizations, and to improve the environment to supply human resources demanded by economic societies, surveys and discussions were given on the external accreditation system for engineer education such as in universities and other organizations. In the field of civil engineering, a special sub-committee was organized, and in advance to a trial examination, surveys and discussions were executed by participating in the actual examination of the engineer educational program at the engineering department of Auckland University, and by participating in the ABET trial examination by the civil engineering department of Kansas State University and the engineering department of Stanford University in the U.S.A. The trial examination was performed upon selecting the engineer educational programs of the civil engineering department of Kinki University and Tottori University. This paper describes the fundamental policies on the educational program examination work for the field of civil engineering, the self-assessment under the educational program, the direction of engineering qualification and educational accreditation, the fundamental concept of examination and accreditation and evaluation process, the works done by the civil engineering section of the science and engineering department of Kinki University, and the works done by the civil engineering section of the engineering department of Tottori University. (NEDO)

A Framework for Performing V&V within Reuse-Based Software Engineering

Science.gov (United States)

Addy, Edward A.

1996-01-01

Verification and validation (V&V) is performed during application development for many systems, especially safety-critical and mission-critical systems. The V&V process is intended to discover errors, especially errors related to critical processing, as early as possible during the development process. Early discovery is important in order to minimize the cost and other impacts of correcting these errors. In order to provide early detection of errors, V&V is conducted in parallel with system development, often beginning with the concept phase. In reuse-based software engineering, however, decisions on the requirements, design and even implementation of domain assets can be made prior to beginning development of a specific system. In this case, V&V must be performed during domain engineering in order to have an impact on system development. This paper describes a framework for performing V&V within architecture-centric, reuse-based software engineering. This framework includes the activities of traditional application-level V&V, and extends these activities into domain engineering and into the transition between domain engineering and application engineering. The framework includes descriptions of the types of activities to be performed during each of the life-cycle phases, and provides motivation for the activities.

Implementation and qualification of MCNP 5 through the intercomparison with the benchmark for the calculation of critical systems Godiva and Jezebel

International Nuclear Information System (INIS)

Lara, Rafael G.; Maiorino, Jose R.

2013-01-01

This work aimed at the implementation and qualification of MCNP code in a supercomputer of the Universidade Federal do ABC, so that may be available a next-generation simulation tool for precise calculations of nuclear reactors and systems subject to radiation. The implementation of this tool will have multidisciplinary applications, covering various areas of engineering (nuclear, aerospace, biomedical), radiation physics and others

Recruitment, qualification and training of personnel for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2005-01-01

The objective of this Safety Guide is to outline the various factors that should to be considered in order to ensure that the operating organization has a sufficient number of qualified personnel for safe operation of a nuclear power plant. In particular, the objective of this publication is to provide general recommendations on the recruitment and selection of plant personnel and on the training and qualification practices that have been adopted in the nuclear industry since the predecessor Safety Guide was published in 1991. In addition, this Safety Guide seeks to establish a framework for ensuring that all managers and staff employed at a nuclear power plant demonstrate their commitment to the management of safety to high professional standards. This Safety Guide deals specifically with those aspects of qualification and training that are important to the safe operation of nuclear power plants. It provides recommendations on the recruitment, selection, qualification, training and authorization of plant personnel. That is, of all personnel in all safety related functions and at all levels of the plant. Some parts or all of this Safety Guide may also be used, with due adaptation, as a guide to the recruitment, selection, training and qualification of staff for other nuclear installations (such as research reactors or nuclear fuel cycle facilities). Section 2 gives guidance on the recruitment and selection of suitable personnel for a nuclear power plant. Section 3 gives guidance on the establishment of personnel qualification, explains the relationship between qualification and competence, and identifies how competence may be developed through education, experience and training. Section 4 deals with general aspects of the training policy for nuclear power plant personnel: the systematic approach, training settings and methods, initial and continuing training, and the keeping of training records. Section 5 provides guidance on the main aspects of training programmes

Recruitment, qualification and training of personnel for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2002-01-01

The objective of this Safety Guide is to outline the various factors that should to be considered in order to ensure that the operating organization has a sufficient number of qualified personnel for safe operation of a nuclear power plant. In particular, the objective of this publication is to provide general recommendations on the recruitment and selection of plant personnel and on the training and qualification practices that have been adopted in the nuclear industry since the predecessor Safety Guide was published in 1991. In addition, this Safety Guide seeks to establish a framework for ensuring that all managers and staff employed at a nuclear power plant demonstrate their commitment to the management of safety to high professional standards. This Safety Guide deals specifically with those aspects of qualification and training that are important to the safe operation of nuclear power plants. It provides recommendations on the recruitment, selection, qualification, training and authorization of plant personnel; that is, of all personnel in all safety related functions and at all levels of the plant. Some parts or all of this Safety Guide may also be used, with due adaptation, as a guide to the recruitment, selection, training and qualification of staff for other nuclear installations (such as research reactors or nuclear fuel cycle facilities). Section 2 gives guidance on the recruitment and selection of suitable personnel for a nuclear power plant. Section 3 gives guidance on the establishment of personnel qualification, explains the relationship between qualification and competence, and identifies how competence may be developed through education, experience and training. Section 4 deals with general aspects of the training policy for nuclear power plant personnel: the systematic approach, training settings and methods, initial and continuing training, and the keeping of training records. Section 5 provides guidance on the main aspects of training programmes

Inspection qualification programme for VVER reactors and review of round robin test results

International Nuclear Information System (INIS)

Horacek, L.; Zdarek, J.

1998-01-01

Experience obtained, especially from in-service inspections of VVER 440-type reactor pressure vessels and from the Czech round test trials with international participation of ultrasonic teams, has highlighted the need for an in-service inspection qualification programme in the Czech Republic focused on NDT procedures, equipment and personnel. Recently, several national and international regional projects included in the PHARE programme (projects 4.1.2/93 and 1.02/94), briefly described, have been initiated. These projects are to cover step by step the programme of the in-service inspection qualification in view of technical justification as well as of practical assessment-performance demonstration-for all the main VVER-type primary circuit components. (orig.)

5 CFR 531.212 - Superior qualifications and special needs pay-setting authority.

Science.gov (United States)

2010-01-01

... 5 Administrative Personnel 1 2010-01-01 2010-01-01 false Superior qualifications and special needs... Appointment Or Position Changes § 531.212 Superior qualifications and special needs pay-setting authority. (a) Agency authority. (1) An agency may use the superior qualifications and special needs pay-setting...

Training and qualification of nuclear power plant operators (4)

International Nuclear Information System (INIS)

Ohsuga, Y.

2009-01-01

Training center using the simulators, instructor training, training upgrade, deployment of digital control panel and review of training were described with overseas practice. Recently, nuclear power plant on-site simulators were also used for respective operator training. Operator teamwork training, training team performance upgrade, reflection of operating experiences in nuclear power plant accidents, development of training support equipments and management of training records were needed to review and upgrade training and qualification programs. (T. Tanaka)

Performance analysis and dynamic modeling of a single-spool turbojet engine

Science.gov (United States)

Andrei, Irina-Carmen; Toader, Adrian; Stroe, Gabriela; Frunzulica, Florin

2017-01-01

The purposes of modeling and simulation of a turbojet engine are the steady state analysis and transient analysis. From the steady state analysis, which consists in the investigation of the operating, equilibrium regimes and it is based on appropriate modeling describing the operation of a turbojet engine at design and off-design regimes, results the performance analysis, concluded by the engine's operational maps (i.e. the altitude map, velocity map and speed map) and the engine's universal map. The mathematical model that allows the calculation of the design and off-design performances, in case of a single spool turbojet is detailed. An in house code was developed, its calibration was done for the J85 turbojet engine as the test case. The dynamic modeling of the turbojet engine is obtained from the energy balance equations for compressor, combustor and turbine, as the engine's main parts. The transient analysis, which is based on appropriate modeling of engine and its main parts, expresses the dynamic behavior of the turbojet engine, and further, provides details regarding the engine's control. The aim of the dynamic analysis is to determine a control program for the turbojet, based on the results provided by performance analysis. In case of the single-spool turbojet engine, with fixed nozzle geometry, the thrust is controlled by one parameter, which is the fuel flow rate. The design and management of the aircraft engine controls are based on the results of the transient analysis. The construction of the design model is complex, since it is based on both steady-state and transient analysis, further allowing the flight path cycle analysis and optimizations. This paper presents numerical simulations for a single-spool turbojet engine (J85 as test case), with appropriate modeling for steady-state and dynamic analysis.

Experience on environmental qualification of safety-related components for Darlington Nuclear Generating Station

International Nuclear Information System (INIS)

Yu, A.S.; Kukreti, B.M.

1987-01-01

The proliferation of Nuclear Power Plant safety concerns has lead to increasing attention over the Environmental Qualification (EQ) of Nuclear Power Plant Safety-Related Components to provide the assurance that the safety related equipment will meet their intended functions during normal operation and postulated accident conditions. The environmental qualification of these components is also a Licensing requirement for Darlington Nuclear Generating Station. This paper provides an overview of EQ and the experience of a pilot project, in the qualification of the Main Moderator System safety-related functions for the Darlington Nuclear Generating Station currently under construction. It addresses the various phases of qualification from the identification of the EQ Safety-Related Components List, definition of location specific service conditions (normal, adbnormal and accident), safety-related functions, Environmental Qualification Assessments and finally, an EQ system summary report for the Main Moderator System. The results of the pilot project are discussed and the methodology reviewed. The paper concludes that the EQ Program developed for Darlington Nuclear Generating Station, as applied to the qualification of the Main Moderator System, contained all the elements necessary in the qualification of safety-related equipment. The approach taken in the qualification of the Moderator safety-related equipment proves to provide a sound framework for the qualification of other safety-related components in the station

Qualifications Frameworks and Their Conflicting Social Imaginaries of Globalisation

Science.gov (United States)

Louise Sarauw, Laura

2012-01-01

Critics often see the European Bologna Process as a univocal standardisation of higher education. By exploring how different qualifications frameworks project different social imaginaries of globalisation, this article takes a different stance. The overarching qualifications framework of the Bologna Process rests on a socially constituted and…

48 CFR 1252.237-70 - Qualifications of contractor employees.

Science.gov (United States)

2010-10-01

... contractor employees. 1252.237-70 Section 1252.237-70 Federal Acquisition Regulations System DEPARTMENT OF....237-70 Qualifications of contractor employees. As prescribed in (TAR) 48 CFR 1237.110(a), insert the following clause: Qualifications of Contractor Employees (APR 2005) a. Definitions. As used in this clause...

WTP Waste Feed Qualification: Hydrogen Generation Rate Measurement Apparatus Testing Report

Energy Technology Data Exchange (ETDEWEB)

Stone, M. E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Newell, J. D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Smith, T. E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Pareizs, J. M. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2016-06-01

The generation rate of hydrogen gas in the Hanford tank waste will be measured during the qualification of the staged tank waste for processing in the Hanford Tank Waste Treatment and Immobilization Plant. Based on a review of past practices in measurement of the hydrogen generation, an apparatus to perform this measurement has been designed and tested for use during waste feed qualification. The hydrogen generation rate measurement apparatus (HGRMA) described in this document utilized a 100 milliliter sample in a continuously-purged, continuously-stirred vessel, with measurement of hydrogen concentration in the vent gas. The vessel and lid had a combined 220 milliliters of headspace. The vent gas system included a small condenser to prevent excessive evaporative losses from the sample during the test, as well as a demister and filter to prevent particle migration from the sample to the gas chromatography system. The gas chromatograph was an on line automated instrument with a large-volume sample-injection system to allow measurement of very low hydrogen concentrations. This instrument automatically sampled the vent gas from the hydrogen generation rate measurement apparatus every five minutes and performed data regression in real time. The fabrication of the hydrogen generation rate measurement apparatus was in accordance with twenty three (23) design requirements documented in the conceptual design package, as well as seven (7) required developmental activities documented in the task plan associated with this work scope. The HGRMA was initially tested for proof of concept with physical simulants, and a remote demonstration of the system was performed in the Savannah River National Laboratory Shielded Cells Mockup Facility. Final verification testing was performed using non-radioactive simulants of the Hanford tank waste. Three different simulants were tested to bound the expected rheological properties expected during waste feed qualification testing. These

Qualification of electrical equipment. A United States nuclear system supplier perspective

International Nuclear Information System (INIS)

Jordan, W.G.

1978-01-01

At Westinghouse Pressurized Water Reactor Systems Division (PWR-SD) qualification. of safety related electrical equipment can be segregated into three distinct generations: (1) the initial seismic and environmental qualification programs for electrical equipment (1969-1972); (2) the supplemental sismic and environmental qualification programs (1975-1977); and (3) the seismic and environmental qualification programs to meet IEEE-323-1974, IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations''(1975). The latter two programs (in a licensing framework), as they are most current, with emphasis on electrical equipment (e.g. transmitters, rack mounted equipment) as opposed to electro-mechanical equipment (valve operators, pump motors) are reviewed. (author)

Engineering Undergraduates' Views of A-Level Mathematics and Further Mathematics as Preparation for Their Degree

Science.gov (United States)

Darlington, Ellie; Bowyer, Jessica

2017-01-01

An ongoing reform programme of the post-16 Advanced "A"-level qualifications in England and Wales means that pre-university mathematics content and assessment will change from 2017. Undergraduate engineering is a subject that relies heavily on mathematics, and applicants to engineering degree programmes in the UK are required to have…

Seismic qualification of non-safety class equipment whose failure would damage safety class equipment

International Nuclear Information System (INIS)

LaSalle, F.R.

1991-01-01

Both Code of Federal Regulations, Title 10, Part 50, and US Department of Energy Order 6340.1A have requirements to assess the interaction of non-safety and safety class structures and equipment during a seismic event to maintain the safety function. At the Hanford Site, a cost effective program has been developed to perform the evaluation of non-safety class equipment. Seismic qualification is performed by analysis, test, or upgrading of the equipment to ensure the integrity of safety class structures and equipment. This paper gives a brief overview and synopsis that address design analysis guidelines including applied loading, damping values, component anchorage, allowable loads, and stresses. Test qualification of equipment and walkdown acceptance criteria for heating ampersand ventilation (H ampersand V) ducting, conduit, cable tray, missile zone of influence, as well as energy criteria are presented

Engineering data of seamate:II, 2

International Nuclear Information System (INIS)

Tanaka, Susumu; Okada, Sohei; Ito, Masayuki; Kusama, Yasuo; Yoshida, Kenzo; Nakase, Yoshiaki.

1981-09-01

SEAMATE-II (Simulated Environmental Apparatus for Material Testing) was constructed in order to establish methodologies for the test of electrical cables under the conditions of postulated LOCA including radiation, and to provide the engineering data for designing the qualification testing facility. A part of engineering data have been previously reported on rapid heating of the inside of the pressure vessel with its outlet valve closed. The engineering data reported here are as follows, 1) controllability of the control devices at rapid heating, 2) comparison of the temperature control systems based on temperature detection, pressure detection and temperature converted from detected pressure, 3) controllability of the automatic control system during rapid heating and rapid cooling, 4) quantities of steam and cooling water required for the automatic control. (author)

Qualification of a production and packaging hot cell for sodium pertechnetate Tc 99m

International Nuclear Information System (INIS)

Cavero, Luis; Robles, Anita; Miranda, Jesus; Martinez, Ramos; Paragulla, Wilson; Moore, Mariel; Herrera, Jorge; Ocana, Elias; Portilla, Arturo; Otero, Manuel; Novoa, Carlos; Koga, Roberto

2014-01-01

It was designed and implemented a protocol for a hot cell of production and packaging of sodium pertechnetate Tc 99m, in a two-step process: installation qualification (IQ) and operation qualification (OQ). In the IQ design specifications and user requirements and associated equipment and materials by traceable documentation was verified. In the OQ scheduled for operation and control sequences it was verified plus operational tests recommended by the World Health Organization (WHO) and ISO 14644-1 and 3 were performed to clean areas. The results showed that the hot cell complies with the classification for Grades C and A for the preparation and packaging of Tc 99m. (authors).

Performance test of remote controlled engineering vehicle system for CBRN threat. Countermeasure performance for CBRN-environment

International Nuclear Information System (INIS)

Naruse, Masahiro; Uemura, Keisuke; Morishita, Masahiro

2015-01-01

A research of 'remote controlled engineering vehicle system for CBRN threat' was triggered by the nuclear accident that successively happened after the Great East Japan Earthquake. This project focuses on the remote controlled engineering system that can be used for multi purposes such as debris/obstacle clearing operation or various reconnaissance operation, under CBRN threat. For the remote-controlled engineering vehicle, we conducted a series of validation tests for countermeasure performance for CBRN-environment. As a result, it is proved that the vehicle possess required performances for CBRN threat. (author)

Comparative engine performance and emission analysis of CNG and gasoline in a retrofitted car engine

International Nuclear Information System (INIS)

Jahirul, M.I.; Masjuki, H.H.; Saidur, R.; Kalam, M.A.; Jayed, M.H.; Wazed, M.A.

2010-01-01

A comparative analysis is being performed of the engine performance and exhaust emission on a gasoline and compressed natural gas (CNG) fueled retrofitted spark ignition car engine. A new 1.6 L, 4-cylinder petrol engine was converted to the computer incorporated bi-fuel system which operated with either gasoline or CNG using an electronically controlled solenoid actuated valve mechanism. The engine brake power, brake specific fuel consumption, brake thermal efficiency, exhaust gas temperature and exhaust emissions (unburnt hydrocarbon, carbon mono-oxide, oxygen and carbon dioxides) were measured over a range of speed variations at 50% and 80% throttle positions through a computer based data acquisition and control system. Comparative analysis of the experimental results showed 19.25% and 10.86% reduction in brake power and 15.96% and 14.68% reduction in brake specific fuel consumption (BSFC) at 50% and 80% throttle positions respectively while the engine was fueled with CNG compared to that with the gasoline. Whereas, the retrofitted engine produced 1.6% higher brake thermal efficiency and 24.21% higher exhaust gas temperature at 80% throttle had produced an average of 40.84% higher NO x emission over the speed range of 1500-5500 rpm at 80% throttle. Other emission contents (unburnt HC, CO, O 2 and CO 2 ) were significantly lower than those of the gasoline emissions.

Experimental study of DI diesel engine performance using biodiesel blends with kerosene

Energy Technology Data Exchange (ETDEWEB)

Azad, A.K.; Ameer Uddin, S.M.; Alam, M.M. [Department of Mechanical Engineering, Bangladesh University of Engineering and Technology, Dhaka-1000 (Bangladesh)

2013-07-01

The experimental investigation offers a comprehensive study of DI diesel engine performance using bio-diesel from mustard oil blends with kerosene. The vegetable oil without trans-esterification reaction have been blended with kerosene oil by volume in some percentage like 20%, 30%, 40% and 50% which have been named as M20 (20% mustard, 80% kerosene), M30 (30% mustard, 70% kerosene), M40 (40% mustard, 60% kerosene) and M50 (50% mustard, 50% kerosene). The properties of the bio-fuel blended with kerosene have been tested in the laboratories with maintaining different ASTM standards. Then a four stroke, single cylinder, direct injection diesel engine has been mounted on the dynamometer bed for testing the performance of the engine using the bio-diesel blends. Several engine parameters like bsfc, bhp, break mean effective pressure, exhaust gas temperature, lube oil temperature, sound level etc. have been determined. A comparison has been made for engine performance of different bio-diesel blends with kerosene with the engine performance of diesel fuel.

An analytical and experimental study of performance on jatropha biodiesel engine

Directory of Open Access Journals (Sweden)

Ganapathy Thirunavukkarasu

2009-01-01

Full Text Available Biodiesel plays a major role as one of the alternative fuel options in direct injection diesel engines for more than a decade. Though many feed stocks are employed for making biodiesel worldwide, biodiesel derived from domestically available non-edible feed stocks such as Jatropha curcas L. is the most promising alternative engine fuel option especially in developing countries. Since experimental analysis of the engine is pricey as well as more time consuming and laborious, a theoretical thermodynamic model is necessary to analyze the performance characteristics of jatropha biodiesel fueled diesel engine. There were many experimental studies of jatropha biodiesel fueled diesel engine reported in the literature, yet theoretical study of this biodiesel run diesel engine is scarce. This work presents a theoretical thermodynamic study of single cylinder four stroke direct injection diesel engine fueled with biodiesel derived from jatropha oil. The two zone thermodynamic model developed in the present study computes the in-cylinder pressure and temperature histories in addition to various performance parameters. The results of the model are validated with experimental values for a reasonable agreement. The variation of cylinder pressure with crank angle for various models are also compared and presented. The effects of injection timing, relative air fuel ratio and compression ratio on the engine performance characteristics for diesel and jatropha biodiesel fuels are then investigated and presented in the paper.

Simulating Large Area, High Intensity AM0 Illumination – Test Results from Bepicolombo and Solar Orbiter Qualification

Directory of Open Access Journals (Sweden)

Oberhüttinger C.

2017-01-01

Specifically, the following topics will be treated. Different methods like electrical performance, thermo-optical and external quantum efficiency measurements have been used to characterize the behaviour of the solar cells after illumination under these conditions. A special focus has been put on the electrical performance. A comparison to other solar cell qualification tests under solely UV radiation has been undertaken. The results have also been compared to a theoretical model. However, the paper will not cover only characterization results but will also give some insight in challenges experienced during the test execution itself. Deviating from other solar cell qualification tests, a representatively equipped photovoltaic assembly on carbon fibre reinforced cyanate has also been included. On these coupon segments, solar cell assemblies connected to shunt diodes and placed next to optical surface reflectors have been exposed to AM0 illumination to qualify the solar cells including their surroundings which therefore covers also contamination effects. Last but not least, first results from the Solar Orbiter qualification are presented. This test with additional 1000 hours and increased intensity has been completed recently.

Qualification guideline of the German X-ray association (DRG) und the German association for interventional radiology and minimal invasive therapy (DeGIR) for the performance of interventional-radiological minimal invasive procedures on arteries and veins

International Nuclear Information System (INIS)

Buecker, A.; Gross-Fengels, W.; Haage, P.; Huppert, P.; Landwehr, P.; Loose, R.; Reimer, P.; Tacke, J.; Vorwerk, D.; Fischer, J.

2012-01-01

The topics covered in the qualification guideline of the German X-ray association (DRG) und the German association for interventional radiology and minimal invasive therapy (DeGIR) for the performance of interventional-radiological minimal invasive procedures on arteries and veins are the following: Practical qualification: aorta iliac vessels and vessels in the upper and lower extremities, kidney and visceral arteries, head and neck arteries, dialysis shunts, veins and pulmonary arteries, aorta aneurysms and peripheral artery aneurysms. Knowledge acquisition concerning radiation protection: legal fundamentals, education and training, knowledge actualization and quality control, definition of the user and the procedure, competence preservation.

ENIQ: European Network for Inspection Qualification: Status report

International Nuclear Information System (INIS)

Champigny, F.; Sandberg, U.; Crutzen, S.; Lemaitre, P.

1998-01-01

The European Network for Inspection Qualification (ENIQ) groups the major part of the nuclear power plant operators in the European Union (and Switzerland). The main objective of ENIQ is to co-ordinate and manage at European level expertise and resources for the qualification of NDE inspection systems, primarily for nuclear components. In this paper the main activities, organisation and actual status of ENIQ are discussed. (author)

European methodology for qualification of NDT as developed by ENIQ

International Nuclear Information System (INIS)

Champigny, F.; Sandberg, U.; Engl, G.; Crutzen, S.; Lemaitre, P.

1997-01-01

The European Network for Inspection Qualification (ENIQ) groups the major part of the nuclear power plant operators in the European Union (and Switzerland). The main objective of ENIQ is to co-ordinate and manage at European level expertise and resources for the qualification of NDE inspection systems, primarily for nuclear components. In the framework of ENIQ the European methodology for qualification of NDT has been developed. In this paper the main principles of the European methodology are given besides the main activities and organisation of ENIQ. (orig.)

Optimal Tuner Selection for Kalman-Filter-Based Aircraft Engine Performance Estimation

Science.gov (United States)

Simon, Donald L.; Garg, Sanjay

2011-01-01

An emerging approach in the field of aircraft engine controls and system health management is the inclusion of real-time, onboard models for the inflight estimation of engine performance variations. This technology, typically based on Kalman-filter concepts, enables the estimation of unmeasured engine performance parameters that can be directly utilized by controls, prognostics, and health-management applications. A challenge that complicates this practice is the fact that an aircraft engine s performance is affected by its level of degradation, generally described in terms of unmeasurable health parameters such as efficiencies and flow capacities related to each major engine module. Through Kalman-filter-based estimation techniques, the level of engine performance degradation can be estimated, given that there are at least as many sensors as health parameters to be estimated. However, in an aircraft engine, the number of sensors available is typically less than the number of health parameters, presenting an under-determined estimation problem. A common approach to address this shortcoming is to estimate a subset of the health parameters, referred to as model tuning parameters. The problem/objective is to optimally select the model tuning parameters to minimize Kalman-filterbased estimation error. A tuner selection technique has been developed that specifically addresses the under-determined estimation problem, where there are more unknown parameters than available sensor measurements. A systematic approach is applied to produce a model tuning parameter vector of appropriate dimension to enable estimation by a Kalman filter, while minimizing the estimation error in the parameters of interest. Tuning parameter selection is performed using a multi-variable iterative search routine that seeks to minimize the theoretical mean-squared estimation error of the Kalman filter. This approach can significantly reduce the error in onboard aircraft engine parameter estimation

12 CFR 231.3 - Qualification as a financial institution.

Science.gov (United States)

2010-01-01

... 12 Banks and Banking 3 2010-01-01 2010-01-01 false Qualification as a financial institution. 231.3... RESERVE SYSTEM NETTING ELIGIBILITY FOR FINANCIAL INSTITUTION (REGULATION EE) § 231.3 Qualification as a financial institution. (a) A person qualifies as a financial institution for purposes of sections 401-407 of...

Lower-Level Qualifications as a Stepping Stone for Young People. Occasional Paper

Science.gov (United States)

Oliver, Damian

2012-01-01

Lower-level qualifications (certificate I and II programs) provide little or no immediate return to the individual in terms of increased wages. However, lower-level qualifications are intended to prepare students who would otherwise not be capable of enrolling in and completing a higher-level qualification or making a successful transition into…

Performance of a RBCC Engine in Rocket-Operation

Science.gov (United States)

Tomioka, Sadatake; Kubo, Takahiro; Noboru Sakuranaka; Tani, Koichiro

Combination of a scramjet (supersonic combustion ramjet) flow-pass with embedded rocket engines (the combined system termed as Rocket-based Combined Cycle engine) are expected to be the most effective propulsion system for space launch vehicles. Either SSTO (Single Stage To Orbit) system or TSTO (Two Stage To Orbit) system with separation at high altitude needs final stage acceleration in space, so that the RBCC (Rocket Based Combined Cycle) engine should be operated as rocket engines. Performance of the scramjet combustor as the extension to the rocket nozzle, was experimentally evaluated by injecting inert gas at various pressure through the embedded rocket chamber while the whole sub-scaled model was placed in a low pressure chamber connected to an air-driven ejector system. The results showed that the thrust coefficient was about 1.2, the low value being found to mainly due to the friction force on the scramjet combustor wall, while blocking the scramjet flow pass’s opening to increase nozzle extension thrust surface, was found to have little effects on the thrust performance. The combustor was shortened to reduce the friction loss, however, degree of reduction was limited as friction decreased rapidly with distance from the onset of the scramjet combustor.

SRNL Phase 1 Assessment Of The WAC/DQO And Unit Operations For The WTP Waste Qualification Program

International Nuclear Information System (INIS)

Peeler, D.; Adamson, D.; Bannochie, C.; Cozzi, A.; Eibling, R.; Hay, M.; Hansen, E.; Herman, D.; Martino, C.; Nash, C.; Pennebaker, F.; Poirier, M.; Reboul, S.; Stone, M.; Taylor-Pashow, K.; White, T.; Wilmarth, B.

2012-01-01

The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is currently transitioning its emphasis from a design and construction phase toward start-up and commissioning. With this transition, the WTP Project has initiated more detailed assessments of the requirements related to actual processing of the Hanford Site tank waste. One particular area of interest is the waste qualification program to be implemented to support the WTP. Given the successful implementation of similar waste qualification efforts at the Savannah River Site (SRS), based on critical technical support and guidance from the Savannah River National Laboratory (SRNL), WTP requested the utilization of subject matter experts from SRNL to support a technology exchange to perform a review of the WTP waste qualification program, discuss the general qualification approach at SRS, and to identify critical lessons learned through the support of DWPF's sludge batch qualification efforts. As part of Phase 1, SRNL subject matter experts in critical technical and/or process areas reviewed specific WTP waste qualification information. The Phase 1 review was a collaborative, interactive, and iterative process between the two organizations. WTP provided specific analytical procedures, descriptions of equipment, and general documentation as baseline review material. SRNL subject matter experts reviewed the information and, as appropriate, requested follow-up information or clarification to specific areas of interest. This process resulted in multiple teleconferences with key technical contacts from both organizations resolving technical issues that lead to the results presented in this report. This report provides the results of SRNL's Phase 1 review of the WAC-DQO waste acceptance criteria and processability parameters, and the specific unit operations which are required to support WTP waste qualification efforts. The review resulted in SRNL providing concurrence, alternative methods, or gap identification

SRNL PHASE 1 ASSESSMENT OF THE WAC/DQO AND UNIT OPERATIONS FOR THE WTP WASTE QUALIFICATION PROGRAM

Energy Technology Data Exchange (ETDEWEB)

Peeler, D.; Adamson, D.; Bannochie, C.; Cozzi, A.; Eibling, R.; Hay, M.; Hansen, E.; Herman, D.; Martino, C.; Nash, C.; Pennebaker, F.; Poirier, M.; Reboul, S.; Stone, M.; Taylor-Pashow, K.; White, T.; Wilmarth, B.

2012-05-16

The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is currently transitioning its emphasis from a design and construction phase toward start-up and commissioning. With this transition, the WTP Project has initiated more detailed assessments of the requirements related to actual processing of the Hanford Site tank waste. One particular area of interest is the waste qualification program to be implemented to support the WTP. Given the successful implementation of similar waste qualification efforts at the Savannah River Site (SRS), based on critical technical support and guidance from the Savannah River National Laboratory (SRNL), WTP requested the utilization of subject matter experts from SRNL to support a technology exchange to perform a review of the WTP waste qualification program, discuss the general qualification approach at SRS, and to identify critical lessons learned through the support of DWPF's sludge batch qualification efforts. As part of Phase 1, SRNL subject matter experts in critical technical and/or process areas reviewed specific WTP waste qualification information. The Phase 1 review was a collaborative, interactive, and iterative process between the two organizations. WTP provided specific analytical procedures, descriptions of equipment, and general documentation as baseline review material. SRNL subject matter experts reviewed the information and, as appropriate, requested follow-up information or clarification to specific areas of interest. This process resulted in multiple teleconferences with key technical contacts from both organizations resolving technical issues that lead to the results presented in this report. This report provides the results of SRNL's Phase 1 review of the WAC-DQO waste acceptance criteria and processability parameters, and the specific unit operations which are required to support WTP waste qualification efforts. The review resulted in SRNL providing concurrence, alternative methods, or gap

Qualification Approach for the CMC Nose Cap of X-38

Science.gov (United States)

Weihs, H.; Gülhan, A.

2002-01-01

given by the predicted re-entry loads. Discrete tests on smaller samples representing cut outs of the structure were performed for further qualification which could not be done at the complete assembly due to the limitations of the test facilities (e.g. plasma channel test). In addition to the qualification of the material or coating capability, arc jet tests were performed to check the steps and gaps influence and qualify sealing function at the interfaces between the CMC parts. This paper will give an overview of the thermal and mechanical qualification of the nose cap system. This includes the vibration loads, thermal cycling, mechanical pressure and steps and gaps arc jet tests.

Seismic qualification tests of fans of the NPP of Laguna Verde U-1 and U-2; Pruebas de calificacion sismica de ventiladores de la Central Laguna Verde U1 and U2

Energy Technology Data Exchange (ETDEWEB)

Jarvio C, G.; Garcia H, E. E.; Arguelles F, R.; Vela H, A. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Naranjo U, J. L., E-mail: gilberto.jarvio@inin.gob.mx [Comision Federal de Electricidad, Gerencia de Centrales Nucleoelectricas, Subgerencia de Ingenieria, Carretera Veracruz-Medellin Km 7.5, Dos Bocas, Veracruz (Mexico)

2013-10-15

This work presents the results of the seismic qualification tests applied to the fans that will be installed in the control panels of the three divisions of the diesel generators of the nuclear power plant (NPP) of Laguna Verde, Unit-1 and Unit-2. This seismic qualification process of the fans was carried out using two specimens that were tested in the seismic table (vibrating) of the Engineering Institute of Universidad Nacional Autonoma de Mexico (UNAM), in accordance with the requirements of the standard IEEE 344-1975, to satisfy the established requirements of seismic qualification in the technical specifications and normative documents required by the nuclear standards, in order to demonstrate its application in the diesel generators Divisions I, II and III of the NPP. The seismic qualification tests were developed on specimens that were retired of the NPP of Laguna Verde recently with a service life of 7.75 years. (Author)

Nuclear criticality safety specialist training and qualification programs

International Nuclear Information System (INIS)

Hopper, C.M.

1993-01-01

Since the beginning of the Nuclear Criticality Safety Division of the American Nuclear Society (ANS) in 1967, the nuclear criticality safety (NCS) community has sought to provide an exchange of information at a national level to facilitate the education and development of NCS specialists. In addition, individual criticality safety organizations within government contractor and licensed commercial nonreactor facilities have developed training and qualification programs for their NCS specialists. However, there has been substantial variability in the content and quality of these program requirements and personnel qualifications, at least as measured within the government contractor community. The purpose of this paper is to provide a brief, general history of staff training and to describe the current direction and focus of US DOE guidance for the content of training and qualification programs designed to develop NCS specialists

Sport Management Interns--Selection Qualifications.

Science.gov (United States)

Cuneen, Jacquelyn; Sidwell, M. Joy

1993-01-01

Examines and rates the background qualifications and qualities, identified by sport management practitioners through an examination of paper credentials, that are desired in interviewees vying for selection into sport management internship positions. (GLR)

Environmental qualification program for Wolsong project

International Nuclear Information System (INIS)

Duggal, A.; Johal, H.; Yee, F.; Suh, S.K.

1995-01-01

The Wolsong EQ Program is a process that begins at the design concept stage and continues throughout the operating life of the station. As all components may not have a 30 year service life without periodic maintenance, the EQ Program becomes an important management tool for the owner of the plant. First, the environmental conditions are predicted for the postulated events. Next, suitably qualified equipment is specified and procured. Then the equipment is installed according to specific instructions. Finally, by means of ongoing maintenance and replacement of parts, the qualification of the equipment is maintained during the operating life of the plant. Proper documentation and traceability is required at all stages of the program. As defined in the Wolsong Project Environmental Qualification Design Guide a comprehensive Environmental Qualification (EQ) Program ensures that safety related equipment located in an area in which a harsh environment could occur, can function when required for the life of the station . This program was implemented at the beginning of the Wolsong project. Using this program, components/equipment are qualified prior to installation and a maintenance program is established to keep equipment 'qualified' throughout the station life

Qualification Paths of Adult Educators in Sweden and Denmark

Science.gov (United States)

Andersson, Per; Kopsen, Susanne; Larson, Anne; Milana, Marcella

2013-01-01

The qualification of adult educators is a central aspect of the quality of adult education. However, within current policy discourses and adult education research on the professional development of prospective adult educators, little attention is paid to teacher qualification when compared to other fields of education and training. In this study,…

The process control and management on equipment qualification of nuclear power plant

International Nuclear Information System (INIS)

Liu Dong; Wang Hongyin; Zhang Yong

2013-01-01

The equipment qualification (EQ) to the safety class equipment is an important safety measure for the nuclear power plants (NPP), and also reflects the nuclear safety culture. Along with the continuous constructions of NPP in China, it has become an important issue for NPP engineering company and equipment suppliers how to effectively establish standard EQ process control and management, and provide sufficient technical arrangements to maintain this EQ management system. This paper summarizes three process of EQ including Design Input, EQ Establishment and EQ Maintenance, proposes the measures and key points for EQ process control and management in phase of NPP construction, and introduces the documents management during the whole process of EQ. (authors)